List of archived documents and
reports from the
NEA Committee
on Reactor Physics (1973-1993)
NEACRP-A Series
In order to find out whether
you have access to any of these documents
please submit
an enquiry to the NEA
Secretariat.
NEACRP-A- 217
Check List of Working Rules of the Nuclear Energy Agency
Committee on Reactor Physics
April 1974
NEACRP-A- 218
Report on the Activities of the NEA Neutron Data
Compilation Centre of Interest to NEACRP
March 1973 - March 1974
NEACRP-A- 219
Report on the Activity of the NEA Computer Program Library
of Interest to NEACRP
May 1973 - May 1974
NEACRP-A- 220
The Physics of CANDU On-Power Fuelling: from Design
Objective to Pickering Demonstration
Pasanen, A.A.
NEACRP-A- 221
Report on the IAEA Workshop on 'Fusion Reactor Design
Problems' held in
Culham (UK) on 29th Jan. - 15th Feb. 1974
Spano, A.H.
30th May 1974
NEACRP-A- 222
On the Validity of Adjusted Cross Sections
Kuroi, H. and Hirota, J.
May 1974
NEACRP-A- 223
Comments on Sodium Void Effect
Shirakata, K., Kuroi, H. and Hirota, J.
May 1974
NEACRP-A- 224
Some Recent Results of Sodium Void Analysis and Related
Problems
(PNC CN 241 74-2)
Zukeran, A., Iijima, S., Yamamoto, M. and Kobayashi, T.
May 1974
NEACRP-A- 225
Review of Fast Reactor Physics Activities Relevant to
LMFBR Programme in PNC (Japan)
(PNC SN 241 74-05)
Kobayashi, S.
June 1974
NEACRP-A- 226
International Symposium on Physics of Fast Reactors
(Report), held in Tokyo
16th - 19th October 973
NEACRP-A- 227
Report on the 17th EANDC Meeting, held in Tokyo
Hirota, J.
25th - 29th March 1974
NEACRP-A- 228
Discussion of Target Accuracies of Core Power
Distributions in Light Water Reactors
Norinder, O.
May 1974
NEACRP-A- 229
A Review of the Sodium Void Coefficient and Ways of
Reducing it to Produce Safer Fast Reactors
Smith, M.F.
April 1974
NEACRP-A- 230
The Analysis of One-Dimensional Reactor Kinetic Benchmark
Computations
Sidell, J.
NEACRP-A- 231
CSEWG Benchmark Specifications
1974
NEACRP-A- 232
Target Accuracies for Commercial-Sized Reactors
Lewellen, J.W.
1974
NEACRP-A- 233
The Accuracy in the Prediction of Physics Parameters of
Fast Breeder Reactor
(PNC SN 241 74-04)
Kobayashi, A. and Kinjo, K.
June 1974
NEACRP-A- 234
Summary Record of the Seventeenth Meeting of the NEACRP,
held at Cadarache, (France)
E. Hellstrand
4th-7th June 1974
NEACRP-A- 235
CCDN: Past, Present, Future
June 1974
NEACRP-A- 236
Adjustments of Neutron Data from ENDF/B-III by Using
Integral Data in a Least-Squares Fit
Haeggblom, H.
June 1974
NEACRP-A- 237
Reactor Physics Aspects of the Oklo Phenomenon
Naudet R.
NEACRP-A- 238
Comparison of the Cross-Section Sensitivity of the Tritium
Breeding Ratio in Various Fusion-Reactor Blankets (ORNL-TM-4696)
Alsmiller, Jr., R.G., Santoro, R.T., Barish, J. and
Gabriel, T.A.
October 1974
NEACRP-A- 239
Progress Report on the Activities of the NEA Committee on
the Safety of Nuclear Installations,
note prepared by the CSNI Secretariat for the 18th meeting
of the NEA-CRP
NEACRP-A- 240
Fission Product Afterheat at Short Times (10 - 104 sec)
after Shutdown
James, M.F.
June 1975
NEACRP-A- 241
Estimation of Decay Data for Short-Lived Fission Products,
Decay Heat Nuclear Data Working Group of the Japanese Nuclear Data
Committee
June 1975
NEACRP-A- 242
Reactor Physics Aspects of Gas-Cooled Fast Reactors (in
German) , except from KFK 2375/EUR 4575 (1973)
NEACRP-A- 243
Design and Safety Considerations for 1000 MWe Gas-Cooled
Fast Reactor
Dalle Donne, M. and Goetzmann, C.A.
NEACRP-A- 244
Preliminary Results of Integral Experiment on
Fusion-Fission Hybrid Blanket Assemblies
Maekawa, H. and Seki, Y.
May 1975
NEACRP-A- 245
Experiments on Neutron Streaming along Void Channels
Kaneko, Y. and Tsuchihashi, K.
NEACRP-A- 246
Outline of Model and Calculations for Proposed Internal
Collaboration Exercise to Discover the Dependence of Reactor
Performance Properties on the Choice of Nuclear Data
NEACRP-A- 247
Proposed Standard Group Structure for Nuclear Data for
Reactors
Askew, J.R., Butler, J., Campbell, C.G. and Rowlands, J.L.
June 1975
NEACRP-A- 249
Summary Record of the Decisions and Conclusions Reached by
the NEA-CRP
at its Eighteenth Meeting, held at C.D.C. Bologna (Italy)
Royen, J.
9th - 13th June 1975
NEACRP-A- 250
Fission Product Data for Nuclear Technology Applications
Hemming, P.
NEACRP-A- 251
Transformation of Actinides and Fission Products by
Neutron Irradiation
Hemming, P.
NEACRP-A- 252
U.S. Results for the IAEA Three-Dimensional Neutron
Diffusion Problem
NEACRP-A- 253
The transmutation of Radioactive Reactor Waste (Australian
Atomic Energy Commission)
J.R. Harries
NEACRP-A- 254
Concepts for the Nuclear Transmutation of Radioactive
Waste from Fission Reactors at present under discussion
Hage, W., Schmidt, E.
NEACRP-A- 255
Summary Record of the 18th Meeting of the NEACRP
Committee, Bologna (Italy)
9-13 June 1975
NEACRP-A- 256
NEACRP Benchmark BWR Lattice Cell Problems (UK) (2 parts)
J.R. Askew (part 1), M.J. Halsall (part 2), 1976
NEACRP-A- 258
Review of Fast Reactor Physics Activities relevant to
LMFBR Programme in PNC, (Japan)
T. Inoue
NEACRP-A- 259
Some Reactor Physics Problems related to LMFBR Safety
(Japan)
K. Aizawa, T. Inoue
NEACRP-A- 260
A Study of Anisotropic Diffusion Effect in Plate Lattice
Assembly (Japan)
K. Shirakata, T. Iijima, K. Yamagishi
NEACRP-A- 261
Treatment of Cruciform Control Rods in CASMO (Sweden)
Malte Edenius
NEACRP-A- 262
Intercomparison of Fission Chamber Standard (UK)
J.E. Sanders
NEACRP-A- 263
Summary of Current NEACRP Views on Fast Reactor Breeding
Assessment (France)
J.Y. Barre
NEACRP-A- 264
Brief Review of Fusion-Reactor Neutronics in the US
F.C. Maienschein
NEACRP-A- 265
Benchmark Calculation of DT Fusion Machine (Italy)
NEACRP-A- 266
Bidimensional Calculation of Neutron Flux for JET Outline
(Italy)
Edmondo Pedretti & Luciano Tondinelli
NEACRP-A- 267
Neutronic and Photonic Studies on Fusion Reactor Blankets
with Low Lithium and Tritium Inventories (Netherlands)
K.A. Vorschuur, H. Brockmann
NEACRP-A- 268
On the Possibility of using a Plasma Focus Machine as
Neutron Source for Cross-Section Measurements by the Activation Method
(Italy)
R. Abbondanza, E. Pedretti
NEACRP-A- 269
On the Prospects of Mixed Fusion-Fusion Energy Systems
(Italy)
Ugo Farinelli
NEACRP-A- 270
Radioactivity and Afterheat of FINTOR and Related Problems
of Maintenance and Waste Disposal (EURATOM)
NEACRP-A- 271
Sensitivity Analysis of Cross-Section Uncertainties
related to the JET Machine (Italy)
NEACRP-A- 272
Specifications for an Internal Comparison Calculation of a
large Sodium-cooled Fast Breeder Reactor (US)
NEACRP-A- 273
Some Comments on the Impact of Thermal Near Breeders on
Uranium Utilization (US)
C.E. Till, Y.I. Chang
NEACRP-A- 274
Simulation of an HCDA Sequence on the ZPPR Critical
Facility (US)
R.E. Kaiser, C.L. Beck
NEACRP-A- 275
On the Extrapolation of ZPR Sodium Void Measurements to
the Power Reactor (US)
C.L. Beck, P.J. Collins, M.J. Lineberry, G.L. Grasseschi
NEACRP-A- 276
Validation results for the DSX Cell Homogenization CODE
(US)
D.C. Wade
NEACRP-A- 277
Model Problems to validate the MC2-II/DSX/Benoist
Procedures for generating Cell-Average Broad Group Cross Sections and
Anisotropic Diffusion Coefficients in ZPR Plate Cells (US)
NEACRP-A- 278
Belgium Plutonium Recycle Program (Belgium)
H. Bairiot, J. Debrue
NEACRP-A- 279
New Developments in Generalized Perturbation Methods in
the Nuclide Field (Italy)
A.Gandini, M. Salvatores, L. Tondinelli
NEACRP-A- 280
Overview of US Activities in Noise Analysis for Nuclear
Power Reactors (US)
R.C. Kryter
NEACRP-A- 281
The Reactor Physics Problems of LMFBR Safety (UK)
A.R. Baker
NEACRP-A- 282
Some suggestions relating to Safety Oriented Work for
NEACRP (UK)
F.J. Fayers
NEACRP-A- 283
Effects of Fast Breeder Characteristics on Consumption and
Expenditures related to Electric Power Generation. An Assessment for
the European Community (EURATOM)
G. Graziani, C. Zanantoni
NEACRP-A- 284
Neutron-Induced Activation in JET (Chapter V from document
EUR-JET-R5)
NEACRP-A- 286
Preliminary announcement of specialist meeting on
cross-sections in structural materials.
NEACRP-A- 287
NEACRP member's reports on national activities on fission
product decay data
NEACRP-A- 288
Summary Record of the 19th Meeting of the Committee
1976
NEACRP-A- 289
Full Minutes of the 19th Meeting of the Committee
NEACRP-A- 291
Consideration of UK., German and French Category I
requests for Nuclear Data
C.G. Campbell, 1977
NEACRP-A- 292
Review of fast reactor physics activities relevant to the
LMFBR programme in PNC (Japan)
T. Inoue
NEACRP-A- 293
Modified diffusion theory analysis of simulated meltdown
experiments (Japan)
Yuji Seki and Makoto Sasaki
NEACRP-A- 294
Test of FP data in JENDC-I by using the integral data
(Japan)
Y. Kikuchi and A. Hasegawa
NEACRP-A- 295
On the physics of LWR-FUGEN (Japan)
T. Haga, M. Matsumoto, H. Kato, and S. Hattori
NEACRP-A- 296
A study on fission rate and gamma-ray heat generation in a
fast reactor (Japan)
K. Koyama, N. Sasamoto, M. Obu, S. Tanaka, Y. Furuta, H.
Kuroi, and J. Hirota
NEACRP-A- 297
Study on sodium void reactivity worth predictional method
(Japan)
T. Kamei, T. Yoshida, K. Murakami, S. Iijima
NEACRP-A- 298
The application of sensitivity analysis to the
identification of data requirements for shielding (UK)
A.K. McCraken
NEACRP-A- 299
The measurement of gamma-ray energy deposition in the
zero-power fast reactor ZEBRA with Li7F thermoluminescent dosimeters
(UK)
A.D. Knipe
NEACRP-A- 300
The sodium void effect: The influence of heterogeneity (UK)
M.J. Grimstone and A.T.D. Butland
NEACRP-A- 301
The sodium void effect: A review of calculational methods
and experiments. (UK)
A.T.D. Butland and M.J. Grimstone
NEACRP-A- 302
Studies of low sodium void reactivity cores (UK)
C.G. Campbell
NEACRP-A- 303
The determination of peak pellet rating (UK)
J.R. Askew
NEACRP-A- 304
The thermoluminescent dosimeter measurement of gamma-ray
energy deposition distributions in reactor shields (USA)
P.N. Stevens, C.E. Clifford, F.J. Muckenthaler, and W. Yoon
NEACRP-A- 305
Recent developments in sensitivity analysis in the US (USA)
E.M. Oblow
NEACRP-A- 306
Fission-product energy release for times following
thermal-neutron fission of 235U between 2 and 14,000 s (USA)
J.K. Dickens, J.F. Emery, T.A. Love, J.W. McConnell, K.J.
Northeutt, R.W. Peelle, and H. Waever
NEACRP-A- 307
Fichier de donnees produits de fission (France)
NEACRP-A- 308
Proposal for GCFR-steam entry benchmarks (Germany)
E.Kiefhaber
NEACRP-A- 309
First comparison of some results obtained at Karlsruhe and
Wuerenlingen for GCFR-steam entry benchmarks (Germany)
E. Kiefhaber
NEACRP-A- 310
Influence of various nuclear data sets on the prediction
of actinides in fast reactor fuel after discharge (Germany)
H. Kuesters and M. Lalovic
NEACRP-A- 311
Announcement of ANL Benchmark Meeting
NEACRP-A- 312
Summary Record of 20th Meeting (Petten)
June 1977
NEACRP-A- 313
Full Minutes of the 20th Meeting of the Committee
NEACRP-A- 314
(Revised) List of NEACRP Category 1 requests
NEACRP-A- 315
Report on GEEL Meeting on Cross Sections for Structural
Materials. Recommendations and conclusions from the NEANDC/NEACRP
Specialist Meeting on the neutron data of structural materials for fast
reactors
DEC. 1977
NEACRP-A- 316
Shielding problems in fast reactors. NEACRP review on
status of fast reactor physics
U. Farinelli, R. Nicks, 1978
NEACRP-A- 318
Sensitivity Analysis of Build-up and Decay of Actinides in
Fast Reactors (Japan)
H. Mitani
NEACRP-A- 319
Atomistic Simulation of Radiation Defects in Various
Crystal Structures (Japan)
Y. Taji
NEACRP-A- 320
A Study of the Heterogeneous Core Characteristics (Japan)
K. Tsutsumi
NEACRP-A- 321
NEA Data Bank Report (Secretariat)
NEACRP-A- 322
Comparison of Neutron Diffusion Theory Codes in Two and
Three Space Dimensions using a Sodium Cooled Fast Reactor Benchmark (UK)
A.T.D. Butland
NEACRP-A- 323
The Spatial Averaging of Cross Sections for use in
Transport Theory Reactor Calculations, with an Application to Control
Rod Fine Structure Homogenisation (UK)
J.L. Rowlands et Al.
NEACRP-A- 324
The Effects of Subassembly Heterogeneity and Material
Boundaries on the Sodium Voiding and Doppler Effects in a Sodium Cooled
Fast Reactors (UK)
A.T.D. Butland
NEACRP-A- 325
The Calculation of Streaming Corrected Diffusion
Coefficients for Fast Reactors (UK)
M.H. Grimstone
NEACRP-A- 326
The IAEA Activities in Reactor Physics (IAEA)
E.A. Khodarev
NEACRP-A- 327
Experimentelle un Theoretische Untersuchungen zur
Reaktivitaetsbindung von Absorberelementen in HTR-systemen (Germany)
V. Drueke et Al.
NEACRP-A- 328
Nodal and Coarse Mesh Codes (Germany)
S. Langenbuch
NEACRP-A- 329
Constants System OSCAR-76 (USSR)
Ju. G. Bobkov
NEACRP-A- 330
The Denatured Uranium-Thorium Fuel Cycle (Canada)
D. Hamel
NEACRP-A- 331
Benchmark Experiments Related to Actinide Production in
Thermal Reactors
(Belgium)
NEACRP-A- 332
Fission-Product Nuclear Data Project Progress Report
(Netherlands)
H. Gruppelaar
NEACRP-A- 333
Information note on dpa calculations (Belgium)
NEACRP-A- 334
Adjustment of evaluated microscopic data on the basis of
evaluated integral experiments (USSR)
L.N. Usachev et Al.
NEACRP-A- 335
Determination of transactinide nuclear data required
accuracy for burn-up calculation in fast reactors (USSR)
L.N. Usachev et Al.
NEACRP-A- 336
A global approach to fuel cycles? (Italy)
U. Farinelli
NEACRP-A- 337
A Preliminary Evaluation of the Technical Aspects of
I.N.F.C.E. (Italy)
U. Farinelli
NEACRP-A- 338
Benchmark Experiments with Thorium in Fast Reactor
Lattices (Switzerland)
U. Schmocker et Al.
NEACRP-A- 339
A U-Pu-Np Cycle in the GCFR (Switzerland)
P. Wydler et Al.
NEACRP-A- 340
Application of Heterogeneous Theory to PWR Studies (UK)
J.R. Askew et Al.
NEACRP-A- 341
Actinide Depletion Studies (USA)
J.W. Lewellen
NEACRP-A- 342
Actinide Monitoring Status Report (Belgium)
G. Birkhoff
NEACRP-A- 343
Neutronics in the Toroidal Belt-Geometry of a Screw Pinch
Reactor (Netherlands)
K.A. Verschuur
NEACRP-A- 344
A Sensitivity Study for Two-Zone Conventional LMFBR Cores
(USA)
P.J. Collins
NEACRP-A- 345
Fuel Handling, Reprocessing and Waste and Related Nuclear
Data Aspects (Germany)
H. Kuesters
NEACRP-A- 346
NEANDC Monographs - Draft Reply (UK)
J.R. Askew
NEACRP-A- 347
NEACRP Documentation Distribution (Secretariat)
NEACRP-A- 348
Summary Record of 21st Meeting (produced in Paris)
NEACRP-A- 349
Specialists Meeting on Calculation of 3-D rating
distributions in operating reactors (Paris)
26th - 28th November 1979
NEACRP-A- 350
Summary Report of discussions at NEA Data Bank
19th January 1979
NEACRP-A- 351
Note from J.J. Schmidt (IAEA). Action 9 of 21st Committee
Meeting - Succession of Transactinide Nuclear Data Meetings (covering
memorandum from J. Rosen)
NEACRP-A- 352
Distribution list for NEACRP Documents (Categories 'A' and
'L' only) - replacing document NEACRP-U-45
NEACRP-A- 353
Summary Record of 21st Meeting (Tokyo) Full Record
6th - 10th November 1978
NEACRP-A- 355
Interim Progress Report on the NEA Data Bank:
(also numbered SEN/DATA (79)5 and NEANDC 119'A')
NEACRP-A- 356
Power peaking and its design margin of JOYO
F. Yoshino
NEACRP-A- 357
A study on the potential safety advantage of heterogeneous
LMFBRs (I)
K. Miyagi et Al.
NEACRP-A- 358
Some correlations between isotopes of Nd, U, Pu and burnup
parameters for the FBR irradiated fuel
S. Nakayama et Al.
NEACRP-A- 359
Criticality computation using the Monte-Carlo Code KENO-4
with a new multi-group constants library
Y. Naito et AL.
NEACRP-A- 360
Report to the NEA Nuclear Data Committee September 1979
Sub-committee on technical activities of the NEANDC
NEACRP-A- 361
Summary of NEACRP views on actinide production and burn-up
J. Hirota et Al.
NEACRP-A- 362
Statement from Dr. Chrien (NEANDC): Exchange of evaluated
nuclear data files between NEA Member countries
NEACRP-A- 363
Report on the 21st Meeting of NEANDC by the NEACRP
observer
J. Debrue
NEACRP-A- 364
Investigations related to the international comparison
calculations of a large sodium-cooled fast breeder reactor
C. Broeders
1979
NEACRP-A- 365
Experimental evidence of isotopic correlations
L. Koch
NEACRP-A- 366
Isotopic correlation techniques - A review.
H. Kuesters, M. Marzo
NEACRP-A- 367
Kinetic Benchmark
H. Kuesters
Munich 1975
NEACRP-A- 368
NEACRP Specialists Meeting on 3-dimensional rating
distributions in operating reactors. Proposed participants at 27.9.79.
NEACRP-A- 369
Critical experiments in a zero-power fast reactor lattice
with breeder zones of thorium and uranium (EIR)
U. Schmocker et Al.
NEACRP-A- 370
Calculation of the multiplication factor of a PWR spent
fuel storage configuration
G. Minsart
NEACRP-A- 371
Requirements for fission-product nuclear data related with
reactor fuel characterization
L. Leenders et Al.
NEACRP-A- 372
"Burnotheque" A valuable standard for accurate burn-up
determination by non-destructive examination
H. Adachi, J. Basselier, L. Leenders
NEACRP-A- 373
NEACRP monograph: "Current status of fast reactor physics"
Reactor coefficients
Argonne National Laboratory
NEACRP-A- 374
Fast reactor fuel cycle studies
Y.I. Chang, C.E. Till
NEACRP-A- 375
Analysis of radial fission rate distributions in ZPPR
cores (ANL)
P.J. Collins
NEACRP-A- 376
LMFBR reactivity surveillance using ex-core detectors
M.J. Lineberry, S.G. Carpenter, C.L. Beck
NEACRP-A- 377
Isotope correlations and measurements in the U.S.
P.J. Persiani
NEACRP-A- 378
Experimental studies of 350 MW(e) Heterogeneous LMFBR
cores at ZPPR
P.J. Collins et Al.
NEACRP-A- 379
Experimental studies of large conventional LMFBR cores at
ZPPR
M.J. Lineberry et Al.
NEACRP-A- 380
Neutronic problems related to the heterogeneous core
concept safety: studies devoted to the sodium effect
J.C. Cabrillat, P. Hammer
NEACRP-A- 381
Actinide cross-sections averaged using the ANL central
spectrum for the NEACRP LMFBR benchmark model
NEACRP-A- 382
Definition des caracteristiques d'un milieu de reference a
combustible oxyde d'uranium enrichi et A K = 1 a partir des mesures
realisees au CEA
J. Bouchard, M. Darrouzet, L. Martin Deidier
NEACRP-A- 383
Comments on the draft Proceedings of the NEACRP/IAEA
Specialists Meeting on the international comparison calculation of a
large sodium-cooled fast breeder reactor
M. Nakagawa
NEACRP-A- 384
Proposal for the third specialists meeting on reactor
noise (SMORN III)
- submission to NEACRP 22nd meeting
Y. Kuroda et AL.
NEACRP-A- 385
Notes on U.S. Fast Reactor Blanket and Shield interface
studies
NEACRP-A- 386
Isotopic correlations in irradiated nuclear fuels (Euratom
Ispra)
C. Foggi
NEACRP-A- 387
A simple comparison of adjusted data sets for iron-based
on measurements in ASPIS and in the cores of fast reactor criticals
M.C.G. Hall
NEACRP-A- 388
Preliminary version of the EURLIB variance-co-variance
matrices
M.C.G. Hall
NEACRP-A- 389
Contribution to the IAEA/NEA Programme of uncertainty
analyses in generic reactors - A sodium-cooled fast reactor
M.C.G. Hall
NEACRP-A- 390
Out-of-Pile critically studies (US)
NEACRP-A- 391
standardized safety analysis of nuclear fuel shipping
containers Robert M. Westfall and Leslie M. Petrie
NEACRP-A- 392
Progress Report of the Dutch Nuclear Data project for fast
reactors covering the period April 78/ Sept. 79
NEACRP-A- 393
The investigation of control rod physics problems in the
large power fast reactor mock-up
Y.A. Kasanskii et Al.
NEACRP-A- 394
Nuclear data and precisions of actinide build-up
calculation in fast reactors
O.D. Bakumenko et Al.
NEACRP-A- 395
Benchmark experiments related to actinide production in
thermal reactors: Experiments in the VENUS critical facility (SCK/CEN,
Mol.)
De. Raedt, Leenders, Minsart,
NEACRP-A- 396
Summary Record of 22nd Meeting of the Committee (Paris)
1st - 5th October 1979
NEACRP-A- 397
Official Summary Record of the 22nd Meeting of the
Committee (Paris)
1st - 5th October 1979
NEACRP-A- 398
Information Sheet - Call for Papers: "Specialist Meeting
on Nuclear Data and Benchmarks for Reactor Shielding (Paris)
27th - 29th October 1980
NEACRP-A- 399
Report by Dr. E. Fort on the 22nd Meeting of NEACRP to the
NEANDC
NEACRP-A- 400
An assessment of the Accuracy Requirements on Higher
Actinide Nuclear Data for Fast Reactors
B.H. Patrick, M.G. Sowerby
NEACRP-A- 401
CSNI/NEACRP Standard Problem Exercise on Criticality Codes
for Spent Fuel Transport Containers
NEACRP-A- 402
NEA Data Bank Activity Report
NEACRP-A- 403
Progress Report on Belgian Contribution to the USNRC
Neutron Transport Theory Blind Test in a LWR Pressure Vessel Benchmark
A. Fabry
NEACRP-A- 404
Information Sheet for SMORN III
NEACRP-A- 405
Integral Studies of Fast Reactor Component Activation in
ZEBRA
J.E. Sanders, W.H. Taylor
NEACRP-A- 406
Experimental Study of Structural Materials Capture in Fast
Breeder Spectra
M. Darrouzet, F. Lyon, G. Rimpault, L. Martin Deidier
NEACRP-A- 407
Note on ENDF/B Structural Data
P.F. Rose, M. Divadeenam, A. Prince
NEACRP-A- 408
Measurements and Calculations for the 235U/Fe Benchmark
Assembly on ZPR-9
R.D. McKnight, D.C. Cade
NEACRP-A- 409
Winfrith Experiment of RETRAN for PWR Pressurized
Transients with Particular Emphasis on ATWS
S.R. Kinnersly
NEACRP-A- 410
Pressurized Transient Studies
B.A. Zolotar
NEACRP-A- 411
Further Studies of Heterogeneity Problems of Plate and Pin
Cells in ZEBRA
J.M. Stevenson
NEACRP-A- 412
Some Problems Related to the Small Zone Experiment Analysis
A.Santamarina
NEACRP-A- 413
Recent Developments in Predicting Sodium Void Reactivities
C.L. Beck, M.J. Lineberry
NEACRP-A- 414
ZPPR Studies of Control Rod Worths in Large Homogeneous
LMFBRs
H.F. McFarlane, P.J. Collins, G.L. Grasseschi, H.A. Harper
NEACRP-A- 415
Experiment Studies of 6000-Litre LMFBR Cores at ZPPR
S.G. Carpenter, P.J. Collins, C.L. Beck, J.M. Gasidlo,
R.W. Goin, R.E. Kaiser, D.W. Maddison, D.N. Olsen
NEACRP-A- 416
A Comparison of Effective Beta Measurements on Plutonium-
and Uranium-Fueled Fast Critical Asemblies
E.F. Bennett
NEACRP-A- 417
Utilization of Information from Operating Reactor JOYO
S. Tamura
NEACRP-A- 418
A Review of the Principles of Correlation Procedures and
the Delilah Method of Correlation, with Application to the Winfrith
SGHW Reactor
A.N. Buckler
NEACRP-A- 419
Reactivity Balance Meter: Feed-Back Effects Measurements
at Phenix
J.C. Gauthier
NEACRP-A- 420
Measurement of Doppler and Thermal Exchange Coefficients
in a PWR by Analyzing the Dynamic Response After a Rod Drop
P. Bernard
NEACRP-A- 421
Experience-to-Theory Feedback in the Development and
Application of core Performance Evaluation Methods
S. Felici, P. Peroni
NEACRP-A- 422
Special Tests at CAORSO Start-up for BWR Simulator Methods
Verification
S. Grifoni
NEACRP-A- 423
Methods of Utilization of Information from Operating
Reactors
B.A. Zolotar
NEACRP-A- 424
The Analysis by Several Neutron Transport Methods of a
Small PWR Model Problem
M.J. Halsall
NEACRP-A- 425
Summary of the Second Technical Meeting on the Nuclear
Transmutation of Actinides
W. Hage
NEACRP-A- 426
Application of Sensitivities to Actinide Build-up Problems
J.C. Estiot, G. Palmiotti, M. Salvatores
NEACRP-A- 427
A Survey of IWGRRM Activities
R. Martinelli
NEACRP-A- 428
Treatment of Internal Rectangular Voids in diffusion Theory
E.M. Gelbard, R.M. Lell, C.H. Adams
NEACRP-A- 429
Preliminary Neutronic Studies of the Compatibility
Problems Between the Heterogeneous and Homogeneous Core
J.C. Cabrillat
NEACRP-A- 430
Flux Tilting in Fast Reactor Systems: Considerations of
System Geometry and Composition on Eigenvalue Separation
Y. Orechwa
NEACRP-A- 431
Neutronic and Thermal-Hydraulic Space-Time Effects in
Large Homogeneous and Heterogeneous LMFBRs
Y. Orechwa
NEACRP-A- 432
A Study on the Potential Safety Advantage of Heterogeneous
LMFBRs (II)
K. Miyagi, H. Laziwara, I. Komatsu, K. Susuki, K. Aoki, I.
Ohtake, T. Inoue, T. Yokoyama
NEACRP-A- 433
Blanket studies at CEA: Status of the Art
M. Salvatores
NEACRP-A- 434
Core instrumentation
B.A. Zolotar
NEACRP-A- 435
Notes on out-of-pile criticality problems
P. Hemming
NEACRP-A- 436
Framework of reactor noise analysis benchmark tests for
SMORN III
Japanese Preparatory Committee of SMORN III
NEACRP-A- 437
Nuclear Data Needs for the analysis of generation and
burn-up of actinide isotopes in nuclear reactors
H. Kuesters
NEACRP-A- 438
Comments on the draft Proceedings of the NEACRP/IAEA
Meeting on International Comparison Calculations
R.D. McKnight
NEACRP-A- 439
Summary Record of 23rd Meeting held at Argonne National
Laboratory,
Idaho Falls (22nd-26th Sept. 1980) also listed as
SEN/NEACRP/M(80)1
NEACRP-A- 440
Summary Record (OFFICIAL VERSION) of 23rd Meeting of the
Committee,
Argonne Nat. Lab. (Idaho Falls)
22nd - 26th Sept. 1980
NEACRP-A- 441
CSNI/NEACRP A Standard problems exercise on criticality
codes for spent fuel transport containers, 1981
NEACRP-A- 442
Summary record of NEACRP ad hoc working group meeting on
evaluation co-ordination
NEACRP-A- 443
Summary record of second NEACRP ad hoc working group
meeting on evaluation co-ordination
NEACRP-A- 444
Participation from and request data for Specialists
Meeting on Fast Neutron Scattering on Actinide Nuclei 23/25 Nov. 81
(also as NEANDC-A-147)
NEACRP-A- 445
Description of the Pin and Plate Geometry Cadenza
assemblies for the international comparison of calculations
J.M. Stevenson, J.L. Rowlands
NEACRP-A- 446
NEA Data Bank Activity Report
NEACRP-A- 447
Proposed International Comparison Calculation of Fast
Reactor Critical Assemblies in Pin and Plate Geometries
NEACRP-A- 448
High Priority Nuclear Data Measurement Requirements
NEACRP-A- 449
Summary Report of 22nd NEANDC Meeting
NEACRP-A- 450
Heterogeneity Effects in MASURCA Rodlet Cells
NEACRP-A- 451
Sodium Void Reactivity Worths in Plate and Pin Cell
Assemblies
NEACRP-A- 452
On the Geometric Modelling Effects for the Pin/Plate
Heterogeneity
Calculation
NEACRP-A- 453
Validation Results for the SDX Cell Homogenization code
for Pin Geometry
NEACRP-A- 454
Space and Angle Finite Element Method for Solving
Three-Dimensional Multi-Group Neutron Transport Problems
NEACRP-A- 455
Reactor Noise Analysis Benchmark Exercise in Connection
with SMORN-III
NEACRP-A- 456
Status of 3D Transport Calculations for Reactors
NEACRP-A- 457
Perturbation Methods for Cutting Costs of Transport
Calculations
NEACRP-A- 458
Tracasyn: A 3D Power Distribution Evaluation Using a
Multi-Channel Synthesis Method from the Results of 2D Transport
Calculations
NEACRP-A- 459
The Solution of the Multigroup Neutron Transport Equation
Using Spherical Harmonics
NEACRP-A- 460
Specifications for a LWR Benchmark Problem with Adjacent
Poisoned Fuel Rods
NEACRP-A- 461
ANL Calculations of the NEACRP LMFBR Depletion Benchmark
Problem
NEACRP-A- 462
Measurements of Fission Products Decay Heat for Fast
Neutron Fissions
NEACRP-A- 463
Decay Heat Measurements and Criticality Control of
Irradiated LWR-Fuel
Elements
NEACRP-A- 464
Beta and Gamma Decay-Heat Measurements for Fast and
Thermal Reactors,
Particularly for Pu-239
NEACRP-A- 465
Fission product Decay Heat from U235 and Pu239 - A Brief
Survey of the
Experimental and Theoretical Data
NEACRP-A- 466
Decay Heat in Fast Power Reactors: Objectives, Qualifying
the Computer
Code
NEACRP-A- 467
Out-of-Pile Subcriticality Monitoring
NEACRP-A- 468
The Qualification of Nuclear Data and Methods for
Post-Irradiation Analysis and Application of Isotopic Correlation
Techniques to Nuclear Safeguards
NEACRP-A- 469
Nuclear Material Safeguards Surveillance and Accountancy
by Isotope Correlation Techniques
NEACRP-A- 470
Recent Development in 238U Capture Measurements
NEACRP-A- 471
Delayed Neutron Data
NEACRP-A- 472
An Analytical Study on Uncertainties of Reactivity Scale
(Beta,eff) of Large LMFBR Cores
NEACRP-A- 473
The Reactivity Scale for Fast Spectrum Criticals
NEACRP-A- 474
RETRAN Validation: Analysis of the LOFT L6-5 Experiment
NEACRP-A- 475
The SPLOSH/SMASH Averaging Problem
NEACRP-A- 476
A Preliminary Study of a Method of Spatial Averaging for
SPLOSH
NEACRP-A- 477
Further Aspects of the Spatial Averaging Problem
NEACRP-A- 478
Transient Effect on Reactivity in Reactor Point Kinetics
Calculation
NEACRP-A- 479
Measurement of Doppler and Heat Transfer Coefficients in
PWR
NEACRP-A- 480
Measurements and Calculations of the Fuel Temperature
Coefficient of
Reactivity for Hinkley Point 'B' AGR
NEACRP-A- 481
Measurements of the Doppler Effect at Phenix
NEACRP-A- 482
Measured and Calculated Pin Power Distributions in the
DODEWAARD BWR
NEACRP-A- 483
Refuelling Analysis of Pin-Fuelled HWR-FUGEN
NEACRP-A- 484
A Study on the Safety and Physics Aspects of Large
Heterogeneous LMFBR's
NEACRP-A- 485
Effects of Cell Asymmetry on the Performance of a Large
Heterogeneous
Critical Assembly
NEACRP-A- 486
Control Rod Experiments in RACINE
NEACRP-A- 487
Recent Developments in Heterogeneous Core Critical
Experiments in the
U.S.
NEACRP-A- 488
Progress in the U.K. Analysis of the BIZET Heterogeneous
Fast Reactor
Assemblies.
NEACRP-A- 489
On the relationship between Local Flux Tilt and Eigenvalue
Separation during delayed Critical Transients in a Fast Reactor.
NEACRP-A- 490
The effects of Intra-Cell Adjoint Flux Heterogeneity on
FOP Reactivity Calculations.
NEACRP-A- 491
Sixth International Conference on Radiation Shielding.
NEACRP-A- 492
Summary Record (full minutes) of the Twenty-Fourth Meeting
of NEACRP.
NEACRP-A- 493
NEA Summary Record of the 24th Meeting of NEACRP.
NEACRP-A- 494
Proceedings of SMORN III.
Pergamon Press
1982
NEACRP-A- 495
Summary Record of 3rd NEACRP ad hoc Working Group Meeting
on Evaluation Coordination, Winfrith, November 1981.
Also as NEANDC 150A
NEACRP-A- 496
Information sheet on Restricted Specialists Meeting on the
NEACRP Benchmark Calculations for fuel burn-up on LMFBR -
April 1982, Cadarache.
NEACRP-A- 497
Information sheet on Restricted Specialists Meeting on
Shielding Benchmark Calculations, 1st/2nd July 1982, Paris.
NEACRP-A- 498
The Winfrith Iron Benchmark Experiment.
M.D. Carter, A.K. McCracken and A. Packwood
NEACRP-A- 499
Summary record of first meeting of Scientific Coordinating
Group of JEF Project.
Also NEANDC 154A
NEACRP-A- 500
High Priority Nuclear Data Measurement Requirements for
the Reactor Programme.
Also NEANDC 156A
NEACRP-A- 501
Fast breeder reactor shielding benchmark results.
NEACRP-A- 502
NEA Data Bank Activity Report, September 1982.
NEACRP-A- 503
Draft proceedings of the NEACRP Specialists' Meeting on
LMFBR Shielding Benchmark, Paris, 1-2 July 1982.
NEACRP-A- 504
Proceedings of the NEACRP Specialists' Meeting on the
"NEACRP LMFBR Benchmark Calculation Intercomparison for Fuel Burn-Up",
Cadarache, 28th to 30th April, 1982.
G. Palmiotti and M. Salvatores
NEACRP-A- 505
Integral Shielding Benchmarks: Status of the EURACOS Iron
and sodium deep penetration experiments JRC, Ispra.
H. Rief
NEACRP-A- 506
Draft PWR shielding benchmark calculation.
G. Hehn
NEACRP-A- 507
Fast neutron flux measurements with the 93Nd(n,n')
reaction - Brief review of the SCK/CEN activities in this field.
H. Tourwe
NEACRP-A- 508
Interlaboratory comparison of fluence neutron dosimeters
in the frame of the PSF start-up measurement programme.
H. Tourwe, F. Kann, A. Fudge, W.L. Zijp, W. Mannhart
and A. Thomas
NEACRP-A- 509
Standardisation and Portability. Activities September 1981
to August 1982 -
NEA Data bank.
NEACRP-A- 510
The FMS Treatment of Gadolinium Burnable Poison in Light
Water Reactors.
H.K. Naess, T. Skardhamar
NEACRP-A- 511
Bizet programme; analysis of subcritical rod worth
measurements in the single annular core BZD/2.
H. Giese, T. Skardhamar
NEACRP-A- 512
Control-rod calculation methods and uncertainties for a
power LMFBR design.
C. Giacommetti, G. Humbert, G. Palmiotti and M.
Salvatores.
NEACRP-A- 513
Homogenization method of pin rods in ZPPR-10A assembly.
T. Takeda, K. Tanimoto and T. Yamamoto.
NEACRP-A- 514
Fast Reactor Control Rod Calculation Methods and
Validation Experiments.
J.L. Rowlands and M.J. Grimstone
NEACRP-A- 515
Calculation methods for control rods in LMFBR's.
H.F. MacFarlane and P.J. Collins
NEACRP-A- 516
A control absorber rod in Phenix: comparison of calculated
and measured worth.
G. Humbert, R. Petiot and P. Coulon
NEACRP-A- 517
Critical experiments of the reactor physics of distorted
cores.
F. Helm and G. Henneges
NEACRP-A- 518
Reactor physics modelling of distorted cores.
W. Maschek
NEACRP-A- 519
Analysis of Fuel slumping experiment on FCA Assembly
VIII-2.
M. Nakano and H.Tsunoda
NEACRP-A- 520
Effect of cell calculation model on the analysis of fuel
slumping experiment.
E. Wachi, T. Takeda and T. Sekiya
NEACRP-A- 521
Burn-up calculations for a BWR Lattice with Adjacent
Poisoned Fuel Rods.
C. Maeder and P. Wydler
NEACRP-A- 522
Monk 6.1 Validation.
G. Walker and R.J. Brissenden.
NEACRP-A- 523
General Considerations on physics and technical aspects
for storage reprocessing, and for shipment of reactor fuel.
H. Kuesters.
NEACRP-A- 524
The CRISTO III Experiment.
A. Santamarina and B. Nouveau.
NEACRP-A- 525
A study on a nuclear criticality safety evaluation
technique.
Y. Naito, J. Kata Kura and M. Tokota
NEACRP-A- 526
Parametric reactivity study of compact PWR fuel storages
including fuel burnup effect.
G. Minsart
NEACRP-A- 527
Evaluation of computational models for spallation and
fission reactions used in an accelerator breeding and transmutation
analysis code.
Y. Nakahara.
NEACRP-A- 528
Some new approaches to the efficient solution of the
transport equation.
C. Budd
NEACRP-A- 529
Monte Carlo Calculations of the WSGHWR using the group
data version of Monk.
J.L. Hutton, P.B. Kemshell and K. Robichaud
NEACRP-A- 530
Group collapsing strategy for 3-D design calculations.
M. Cosimi, C. Giaccometti, G. Palmiotti and M.
Salvatores
NEACRP-A- 531
Recent developments and improvements in the code system
for the neutronic design of fast breeder reactors at CEA.
C. Giacometti, J.C. Estiot, G. Palmiotti, C.
Grondein, G. Le Cardinal, M. Ravier.
NEACRP-A- 532
Iterative Solution of the DFEM Algorithm of the Three
Dimensional Neutron Transport Problems.
T. Fujimara, Y. Nakahara, M. Matsumura.
NEACRP-A- 533
BETA and Gamma-ray decay energy from fragments from the
fission of U235 and Pu 239 in a fast reactor.
W.H. Taylor, M.F. Murphy, M.R. March.
NEACRP-A- 534
A brief survey of experimental and theoretical data on
fission produce decay heat from U235 and Pu239.
M.F. James
NEACRP-A- 535
Informal Memorandum on fast reactor short-term fission
product decay heat and its uncertainty.
R.W. Peelle, J.K. Dickens
NEACRP-A- 536
Measurements of Gamma-ray energy release rates following
fast-neutron fissions of U238, Th232 and natural uranium.
M. Akiyama, S. An
NEACRP-A- 537
Isotope correlations for safeguards surveillance and
accountancy methods.
P.J. Persiani, Kalimollah
NEACRP-A- 538
Subcriticality monitoring by means of the pulsed neutron
technique. Measurements on single PWR-type sub-assemblies.
J. Debrue
NEACRP-A- 539
Applications of calculated isotope correlations in the
determination of the input balance at the La Hague reprocessing plant.
A. Giacometti, R. Girieud
NEACRP-A- 540
Comparison of measured neutron reaction rates in fast
reactor steels with values calculated using FD5 Data.
M.F. Murphy, J.M. Stevenson, W.H. Taylor
NEACRP-A- 541
The importance of electron transport in reactor heating
calculations.
A.D Knipe
NEACRP-A- 542
ANL/AEEW Comparison of reaction-rate ratio techniques in
ZEBRA.
D.W. Maddison, G. Ingram
NEACRP-A- 543
A comparison of central reactor-rate ratio measurement
techniques in BIZET cores.
B. Bohme, B.L.H. Burbidge
NEACRP-A- 544
A comparison of counting and mass spectrometer methods for
measuring U238 capture.
J.M. Gasidlo, D.W. Maddison, R.T. Armani, J.A.
Morman, S.G. Carpenter
NEACRP-A- 545
On the Reactivity Scale for large LMFBR cores.
H. Nakamura, N.Tsugi
NEACRP-A- 546
Recent developments in small sample worths.
K.S. Smith, R.W. Schaefer
NEACRP-A- 547
Benchmark intercomparisons of reactivity worths in an
LMFBR-type plate critical assembly.
L.G. LeSage
NEACRP-A- 548
Comparison of reactivity scales based on Kinetics
measurements and Plutonium fuel worths in eleven ZEBRA assemblies.
J.M. Stevenson
NEACRP-A- 549
Gamma heating measurements in a heterogeneous core
configuration.
D. Calamand
NEACRP-A- 550
Sodium-void reactivity in a heterogeneous LMFBR.
H.F. McFarlane, C.L. Beck, H. Henryson II
NEACRP-A- 551
U.S. Fast critical assembly developments.
M.J. Lineberry
NEACRP-A- 552
Physics assessments of LMFBR integral parameters.
M.J. Lineberry, H.F. McFarlane, P.J. Collins
NEACRP-A- 553
Note in CSNI Activities on Nuclear Criticality Safety
Computations.
R.W. Peelle
NEACRP-A- 554
Draft Notes on the Reduced Enrichment Research and Test
Reactor (RERTR) Program.
L.G. LeSage
NEACRP-A- 555
Investigation of physical characteristics during the
BN-600 Reactor start-up.
Y.A. Kazanski et al.
NEACRP-A- 556
A Study on shielding calculation technique using the
Albedo-SN method.
M. Kawai, J. Itoh
NEACRP-A- 557
The Third Specialists' Meeting on Reactor Noise - A Brief
Overview.
J. Hirota, Y. Shinohara
NEACRP-A- 558
Summary Record of the Second Meeting of the Scientific
Co-ordinating Group,
Antwerp 8th Sept. 1982.
Also NEANDC-A-162
NEACRP-A- 559
Summary Record of 25th Meeting of NEACRP, Karlsruhe,
September 1982
(SEN/NEACRP/M(82)1).
NEACRP-A- 560
Full minutes of 25th Meeting of NEACRP Committee,
Karlsruhe, September 1982.
Also NEANDC-171A
NEACRP-A- 561
List of NEACRP documents A and L categories.
NEACRP-A- 562
Summary Record of 23rd Meeting of NEANDC, 27th Sept./1st
Oct. 1982.
(NEANDC-172'A')
NEACRP-A- 563
Summary Record of 23rd Meeting of NEANDC.
Also NEANDC-A-174, (SEN/NEANDC/M(82)1).
NEACRP-A- 564
Critical assembly descriptions.
B. Richmond
1983
NEACRP-A- 565
Summary Record of the Third JEF Meeting.
Also as NEANDC 175 A
NEACRP-A- 566
Summary record of the 4th meeting of the Scientific
Coordinating Group of the JEF project.
Also NEACRP-566-A
NEACRP-A- 567
Benchmark on Interactive Effects of Gd-poisoned pins in
BWRs, status report.
C. Maeder, P. Wydler
NEACRP-A- 568
High Priority Nuclear Data Measurement Requirements for
the Reactor Programme
(Sept. 83).
Also NEANDC-180-A
NEACRP-A- 569
Summary Record of 26th NEACRP Meeting, Oak Ridge, USA,
17th - 21st October 1983
Also as SEN/NEACRP/M(83)1 and NEANDC-180-A
NEACRP-A- 570
Summary Record (official) of 26th NEACRP Meeting,
OakRidge, USA, 17th - 21st October 1983.
Also as NEANDC-A-181
NEACRP-A- 572
NEANDC Activity Report.
NEACRP-A- 573
MAGIK. A Computer Program to Investigate Transients in AGR
and MAGNOX Reactors.
J.K. Fletcher and M.A. Perks.
NEACRP-A- 574
Ejected Rod Calculation, Kinetic Axial Modelisation.
R. Renain
NEACRP-A- 575
Power Distribution Prediction for a Large Commercial LMFBR.
R. De Wouters and G. Flamenbaum
NEACRP-A- 576
Perturbation Methods for Power Distribution Prediction.
G. Palmiotti and M. Salvatores
NEACRP-A- 577
The Effects of Simplified Control Rod Modelling on
Neutronics Calculations for the Prototype Fast Reactor.
D.J. Lord and T.D. Newton
NEACRP-A- 578
The Prediction of Sub-Assembly Powers Throughout the Fuel
Cycle of a Commercial Fast Reactor.
R.E. Sunderland
NEACRP-A- 579
Radial Dependence of C/E Value in JUPITER-I Core Analysis
Y. Kato, M. Yamamoto, K. Shirakata and T. Takeda
NEACRP-A- 580
ZPPR Data Relevant to the Prediction of Power Distribution
in Large LMFBRs through the Burnup Cycle.
P.J. Collins
NEACRP-A- 581
Thermo Hydraulic Transient Simulation of LMFBRs using
COMMIX-1A Computer Code.
W.L. Baumann, W.T. Sha and H.M. Domanus
NEACRP-A- 582
IFAC Workshop - Modelling and Control of Electric Power
Plants.
NEACRP-A- 583
SALAMANDRE: A Digital Simulator for Light Water
Pressurised Reactors.
P. Bernard, C. Bonnet, J. Chinardet, F. Ducamp, S.
Nisan, J. Romeyer-Dherbery
NEACRP-A- 584
LWHCR Moderator-Voilage Experiments.
R. Chawla, K. Gmuer, H. Hazel and R. Seiler
NEACRP-A- 585
Recycling of Uranium-236.
J.R. Askew
NEACRP-A- 586
The Trend Neutronics Studies concerning the Uranium
Recycle.
C. Golinelli
NEACRP-A- 587
Technical and Economic Aspects of Plutonium Recycling.
O. Beer and P. Schmiedel
NEACRP-A- 588
Investigations on a Tight Lattice PWR in the Federal
Republic of Germany.
H. Kuesters
NEACRP-A- 589
The Superposition Method, A New Approach to Pin Power
Determination.
F. Nissen
NEACRP-A- 590
Comparison of Pin Powers in Thermal Reactors Calculated
from Coarse Mesh Methods.
M. Hamasahi, W. Kawamura and T. Takeda
NEACRP-A- 591
Distributed Heating Calculations for a Fast Reactor
Application to the PFR Equilibrium Core Model.
G. Reddell and A.T.D. Butland
NEACRP-A- 592
The MONK Code and its Validation from Data.
P. Hoge, G. Walker, R.J. Brissenden and D.E. Bendall
NEACRP-A- 593
New Developments on the Critical Eigenvalue Assessment.
R.D. McKnight
NEACRP-A- 594
TRIMARAN: A Three Dimensional Multigroup P1 Monte Carlo
Code for Criticality Studies.
G. Erment
NEACRP-A- 595
Status of CSNI Working Group on Standard Problem Exercises
on Criticality Calculations for Spent Fuel Transport Casks and Arrays
of Fissile Material Packages.
G.E. Whitesides
NEACRP-A- 596
Difficulties with Experiments Involving Arrays of Fissile
Solutions.
J.T. Thomas
NEACRP-A- 597
Generalised Monte Carlo Perturbation Algorithms for
Correlated Sampling and a Second Order Taylor Series Approach.
H. Rief
NEACRP-A- 598
Monte Carlo Depletion Calculation in a Slab.
A.F. Course, M.J. Halsall and J.L. Hutton
NEACRP-A- 599
Production of Fissile Material.
D.E. Bartine and J.O. Johnson
Comments on Out-of-Pile.
NEACRP-A- 600
The LOTUS Fusion-Fission Hybrid Project.
L. Green, P.A. Maldy, A. Kumar, C. Sahraoui and K.
Gmiir
NEACRP-A- 601
Measurements of Reactor Rates in and Around Control Rods
at ZPPR.
P.J. Collins
NEACRP-A- 602
A Homogenisation Method of Control Rods with Neutron
Leakage Effect.
S. Ono and T. Takeda
NEACRP-A- 603
Boron Capture in Boron Carbide Rodlets Irradiated in
PHENIX: An Experiment to Calculation Comparison.
G. Humbert, G. Palmiotti and C. Tourni
NEACRP-A- 604
A Sensitivity Approach to Study Control Rod Worth
Uncertainties.
G. Palmiotti and M. Salvatores
NEACRP-A- 605
Control Rod Worths and Interactions in Fast Reactors.
H. Grese
NEACRP-A- 606
Parametric Studies for the Heterogeneous Core Concept in
the Framework of the PRERACINE and RACINE Experimental Programs.
G. Humbert, K. Kappler, M. Martini, G. Norvez, G.
Rimpault, B. Ruelle,
W. Scholtyssek and A. Stanculescu
NEACRP-A- 607
Validation of Neutronic Calculations for Distorted Core
Configurations arising in Accident Situations of LMFBRs.
H. Kuesters
NEACRP-A- 608
Reactivity Effects of Fuel Rearrangement in Fast Reactor
Rod Bundles.
F. Helm and G. Henneges
NEACRP-A- 609
Measurements and Computation of the Reactivity Effects of
Accident-Caused Core Distortions in Liquid Metal Fast Breeder Reactors.
F. Helm, G. Henneges and W. Maschek
NEACRP-A- 610
Intercomparison of Reaction Rate Measurement Techniques in
MASURCA.
W. Scholtyssek
NEACRP-A- 611
Intercomparison of Reaction Rate Measurement on Fast
Reactors.
D.W. Maddison and S.G. Carpenter
NEACRP-A- 612
The Present Accuracy of Physics Characteristics of
Unirradiated Fast Reactor Cores.
H. Kuesters and S. Pilate
NEACRP-A- 613
Summary of the Meeting "Status of Static Reactor
Calculations in Nordic Countries".
S.-O. Lindahl
NEACRP-A- 614
Progress Report on the International Comparison of
Calculations for the CADENZA Assemblies (the Pin-Plate Benchmark).
M.J. Grimstone, J.L. Rowlands and J.M. Stevenson
NEACRP-A- 615
ANL, Intercomparison of Cell Heterogeneity Effects in Pin
and Plate Geometries.
NEACRP-A- 616
Collision Probabilities for Plate Geometry Cells with an
Approximate Treatment of Plate Edge Regions.
M.J. Grimstone and J.L. Rowlands
NEACRP-A- 617
A Method of Calculating Collision Probabilities for the
Pin Cell Minicalandrier used in Fast Reactor Critical Facilities.
M.J. Grimstone and J.L. Rowlands
NEACRP-A- 618
Results of the NEA PWR Shielding Benchmark.
G. Hehn
NEACRP-A- 619
Adjustment of Neutron Multigroup Cross-sections.
G. Helm, R.-D. Baechle, G. Pfister and M. Mattes, G.
Hehn
NEACRP-A- 620
The Sixth International Conference on Radiation Shielding,
A Brief Overview.
T. Asaoka, T. Lloyds, T. Suzuki and S. Kikuchi
NEACRP-A- 621
Experimental Studies of Radially-Heterogeneous LMFBR
Critical Assemblies a ZPPR.
H.F. McFarlane, S.G. Carpenter, P.J. Collins, D.N.
Olsen and S.B. Brumbach
NEACRP-A- 622
Recent Developments in the Control Worth Discrepancy
K.S. Smith and R.W. Schaefer
NEACRP-A- 623
NEACRP Reactivity Benchmark Proposal.
L.G. LeSage
NEACRP-A- 624
Overview of the Specialists' Meeting on In-Core
Instrumentation and the Assessment of Reactor Nuclear and
Thermal/Hydraulic Performance,
Fredrikstad (Norway), 10-13 October, 1983.
R. Martinelli
NEACRP-A- 625
Summary Record of the Fifth Meeting of the Scientific
Coordination Group of the Joint Evaluated File Project.
Also JEF/DOC-58 with annexes, and NEANDC-A-183
without annexes
NEACRP-A- 626
Summary Record of the 24th Meeting of the NEANDC held in
Tokai-Mura, Japan,
12th-16th March 1984.
Also NEANDC-A-194, (SEN/NEANDC/M(84)1)
NEACRP-A- 627
Sensitivity Analysis and Monte Carlo - the DATAK Code.
M. Armishaw, A.K. McCracken, P.C. Miller
NEACRP-A- 628
The Winfrith Water Benchmark Experiment.
M.D. Carter, A. Packwood
NEACRP-A- 629
Results and Calculational Model of the Winfrith Iron
Benchmark Experiment.
J. Butler, M.D. Carter, A.K. McCracken, A. Packwood
NEACRP-A- 630
The ASPIS Graphite Benchmark Experiment: Part 1
Experimental Data and Preliminary Calculations.
M.D. Carter, P.C. Miller, A. Packwood
NEACRP-A- 631
Summary Record (Official minutes) of the 24th Meeting of
the NEANDC held in Tokai-Mura, Japan, 12th -26th March 1984.
Also as NEANDC-195"A"
NEACRP-A- 632
NEA Specialists' Meeting on Shielding Benchmark, Saclay,
10th November 1984.
NEACRP-A- 633
NEA Data Bank Activity Report, October 1984.
NEACRP-A- 634
Report by the NEA Secretariat on Recent Activities of the
Committee on the Safety of Nuclear Installations of Interest to the
Committee on Reactor Physics.
SINDOC (84)232.
NEACRP-A- 635
The CEA Experimental Program for Validating the Tight
Lattice Reactor Concept
NEACRP-A- 636
Further Investigations in the PROTEUS-LWHCR Phase I
Program,
R. Chawla, K. Gmuer, H. Hager, R. Seiler.
NEACRP-A- 637
Physics Problems on Analysis of High Conversion
Pressurized Water Reactor (HCPWR) with Tighter Pitch Lattices (An
Analysis of PROTEUS-LWHCR Cores by SRAC System).
Yukio Ishiguro, Keichiro Tsuchihashi and Makoto Sasaki.
NEACRP-A- 638
Studies of Pu Recycling in Close-Packed PWR Lattices,
Erik Johansson.
NEACRP-A- 639
Analysis of FCA Assembly X using Monte Carlo and
Deterministic Method,
S. Iijima, M. Nakagawa.
NEACRP-A- 640
Prediction of K-effective and Leakage for Dimple Assembly
S01/20/A using the Monte Carlo Computer Code Monk,
A.F. Course.
NEACRP-A- 641
The Use of the MONK Monte Carlo Code for Whole Core
Calculations for Fast Reactors,
M.J. Grimstone.
NEACRP-A- 642
Monte Carlo Calculations of the Dungeness 'B'
Commissioning Experiments,
I.J. Macbean, K. Robichaud.
NEACRP-A- 643
A Small Reactor Neutronic Problem: Control Rod Efficiency
of the Orphee Reactor calculated by the Monte Carlo Code Tripoli,
L. Bourdet, C. Morin, J.C. Nimal.
NEACRP-A- 644
Whole-Assembly calculations with Monte Carlo,
R.D. McKnight, P.J. Collins.
NEACRP-A- 645
A Monte Carlo Calculation for ZPPR-11B,
P.J. Collins, R.D. McKnight.
NEACRP-A- 646
Generalized Monte Carlo Perturbation Theory using
Derivative Operators and Double Biasing Schemes,
H. Rief.
NEACRP-A- 647
Calculation of Multiplication Factors and Time-Decay
Constants with the Monte Carlo Method,
W. Matthes.
NEACRP-A- 648
Modelling of Reactivity Interaction Effects in the Source
Reactor Nestor,
R.C. Bannerman.
NEACRP-A- 649
GOLEM, A Versatile Scheme of Codes for Reactor Calculation,
J. Porta, J.Y. Doriath
NEACRP-A- 650
Status Report of the RERTR Program,
A. Travelli.
NEACRP-A- 651
Progress Report on Reactor Design,
D.E. Bartine.
NEACRP-A- 652
Analysis on the KUCA MEU Experiments (I),
Seiji Shiroya, Masatoshi Hayashi, Keiji Kanda, Toshikazu
Shibata.
NEACRP-A- 653
Neutronics Design of Upgraded JRR-3 Research Reactor,
H. Tsuruta, H. Ichikawa, J. Iwasaki.
NEACRP-A- 654
USA Contribution Nuclear Data Base Assessment - Group H
Shielding (Chapter X, Section 2),
Yousry Gohar, B.A. Engholm, R.W. Roussin, R.T. Santoro,
A.B. Smith, C.C. Baker.
NEACRP-A- 655
The Neutronics of INTOR/NET,
C. Ponti.
NEACRP-A- 656
Benchmark Experiments on a 60 cm-thick Li2O Slab Assembly
and their Analysis,
H. Kaekawa, Y. Ikeda, Y. Oyama, K. Tsuda, S. Yamaguchi, M.
Nakagawa, T. Fukumoto, A. Hasegawa, T. More, Y. Seki, T. Nakamura.
NEACRP-A- 657
Neutronic Experiments in a 120 cm. Lithium Sphere,
K. Sugiyama, K. Kanda, S. Iwasaki, M. Nakazawa, H.
Hashikura,
T. Iguchi, H. Sekimoto, S. Itoh, K. Sumita, A. Takahashi,
J. Yamamoto.
NEACRP-A- 658
Measurements of Tritium Breeding Ratios in Lithium Slabs
using Rotating Target Neutron Source,
A. Takahashi, K. Yugami, K. Kohno, N. Ishigaki, J.
Yamamoto and K. Sumita
NEACRP-A- 659
Column Bowing and Inserted Reactivity in the HTGR Core,
I. Otake.
NEACRP-A- 660
Bowing Behaviour of Subassemblies in Experimental Fast
Reactor "JOYO",
Tetsuo Ikegami, Nobutatsu Mizoo, Yoshiaki Matsuno, Yoshio
Watari.
NEACRP-A- 661
The Effects of Subassembly Heterogeneity and Material
Boundaries on the Sodium Voiding and Doppler Effects in a Sodium Cooled
Fast Reactor,
A.T.D. Butland.
NEACRP-A- 662
Status of Argonne National Laboratory Methods Development
to treat Heterogeneity Effects in Complex Geometries,
R.N. Hwang.
NEACRP-A- 663
Investigation of "low" and "high" heterogeneity effects
at the BFS-45 critical assembly,
V.A. Dulin, A.V. Shapar.
NEACRP-A- 664
Double Heterogeneity Effects on Criticality and Sodium
Void Calculation of Fast Reactors,
C. Gho, G. Palmiotti, M. Salvatores
NEACRP-A- 665
Study of Neutron Absorption by Fission Products in a
Critical Assembly,
S.M. Bednyakov, V.A. Dulin, G.N. Manturov, V.K. Mozhaev.
NEACRP-A- 666
The ARMA Experiment on Masurca, a Status Report,
W. Scholtyssek, G. Granget.
NEACRP-A- 667
Three-Dimensional Kinetics Analysis of Large LMFBR Cores
with Thermal Hydraulic Feedback,
Y. Oka, N. Tada, M. Konomura, S. Kondo and S. An.
NEACRP-A- 668
Experimental Qualification of PWR Assemblies Calculation
with Gadolinium Burnable Poisons,
P. Chaucheprat, M. Darrouzet, L. Martin-Deidier, A.
Santamarina.
NEACRP-A- 669
Detailed Study on U232 and U236 in Uranium Recycling,
Kazuki Hida, Sadao Kusuno and Ritsuo Yoshioka.
NEACRP-A- 670
Critical Experiment with Thorium using Kuca,
Keiji Kobayashi, Masatoshi Hayashi, Seiji Shiroya,
JeijiKanda, Toshikazu Shibata, Naohiro Hirakawa, Kazutaka Ohashi,
Shigeyasu Sakamoto, Otohiko Aizawa, Yuichi Ogawa, Kasuhiko Kudo.
NEACRP-A- 671
Power Distribution and Control Rod Worth in
Heavy-Water-Moderated, Cluster-type Plutonium Fuelled Core, Experiment
and Analysis,
Toshio Wakabayashi, Nobuo Fukumura, Yuuki Hachiya.
NEACRP-A- 672
Critical Experiments on Poisoned Fuel Rods Containing
0.1-8.0 wt% GD2O3 in Light Water Lattices,
Koichi Sakurada, Makoto Ueda, Yoshihira Ando, Tsutomu
Yokoyama, Takeshi Seino.
NEACRP-A- 673
Local Pin Power Prediction Applying Heterogeneous and
Homogeneous Global Parameter Values,
Flemming Nissen.
NEACRP-A- 674
Measurements of Gamma-Ray Energy Deposition in a
Heterogeneous Reactor Experimental Configuration and their Analysis,
D. Calamand, R. de Wouters, A.D. Knipe, R. Menil.
NEACRP-A- 675
Survey Analysis of Radiation Levels in the HTGR Regions,
C.O. Slater, S.N. Cramer.
NEACRP-A- 676
A U.S. Proposal for an International Intercomparison of
Codes for Heat Transfer Assessment of Transportation Packages.
NEACRP-A- 677
The Large Core Code Evaluation Working Group Benchmark
Problem Four: Neutronics and Burnup Analysis of a Large Heterogeneous
Fast Reactor, Part 1: Analysis of Benchmark Results,
C.L. Cowan R. Protsik, J.W. Lewellen.
NEACRP-A- 678
Some Remarks related to the C/E Trends for Power
Distributions in Large Criticals,
M. Salvatores.
NEACRP-A- 679
Fission Distributions in a Critical Assembly with Two
Internal Breeding Zones,
S.P. Belov, A.I. Novozhilov.
NEACRP-A- 680
Analysis of JOYO Burnup Data and their Interpretation in
terms of Cross-Section Adjustment,
Masatoshi kawashima, Tadashi Yoshida and Tetsuo Ikegami.
NEACRP-A- 681
Radial Power Distribution Bias in the ZPPR-13A 700 MWe
Radial Heterogeneous Reactor Critical Experiment,
Mcfarlane et al.
NEACRP-A- 682
Burnup Sensitivity Analysis in a Fast Breeder Reactor -
Prediction
Accuracy of Burnup Characteristics,
Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda and
Takuya Umano.
NEACRP-A- 683
Burnup Sensitivity Calculation in a Fast Breeder Reactor
with
a Generalized Perturbation Theory,
Toshikazu Takeda and Takuya Omano.
NEACRP-A- 684
Actinide Integral Measurements on FCA for Evaluating and
Improving Their Cross Section Data,
T. Mukaiyama, M. Obu, M. Nakano, S. Okajima, T. Koakutsu.
NEACRP-A- 685
Reduction of Uncertainties on the Components of the
Reactivity
Loss per Cycle - the Balzac Program on Masurca,
A. d'Angelo, N. Karouby-Cohen, G. Palmiotti, G. Rimpault,
M. Salvatores, R. Soule.
NEACRP-A- 686
Analysis on Burnup Characteristics of Experimental Fast
Reactor
"JOYO" MK-I,
Yoshio Watari, Kunikazu Kaneto, Shusaku Sawada, Kazuo
Azekura,
Hiroko Aizawa, Kotaro Inoue, Tetsuo Ikegami.
NEACRP-A- 687
Comparison of Calculated and Experimental Reaction Rate
Distributions and Associated Parameters in the Bizet
Assemblies,
J.M. Stevenson.
NEACRP-A- 688
Pin-Plate Studies - A Comparison of ZPRR-12 and Cadenza
Results,
R.D. McKnight, P.J. Collins.
NEACRP-A- 689
Reactivity Benchmark,
L.G. Lesage
NEACRP-A- 690
Benchmark on Recycling of Reprocessed Uranium,
C. Golinelli, J.C. Guyot
NEACRP-A- 691
Summary Conclusions of an NEACRP Sponsored Specialists'
Meeting
on Methods for Treating Unresolved Resonance Regions in
Neutronics
Calculations, held at OECD Headquarters, Paris, 26-27
January 1984.
NEACRP-A- 692
Report on the 1984 ANS Reactor Physics and Shielding
Topical,
September 17-19, Chicago, IL.
NEACRP-A- 693
Reactor Physics Calculations in connection with the
Development
of a 20% Enriched Fuel Element for DR3,
C.F. Hojerup.
NEACRP-A- 694
Summary Record of the 27th Meeting of NEACRP,
Aix-en-Provence,
22nd-26th October 1984. (Official minutes)
Also NEANDC-A-200, SEN/NEACRP/M(85)1
NEACRP-A- 695
Summary Record of the 27th Meeting of NEACRP,
Aix-en-Provence,
22nd-26th October 1984.
Also NEANDC-A-197
NEACRP-A- 696
Etude des methodes de calcul de l'autoprotection dans les
resonances
1ere partie.
P. Ribon, V. Sauvinet, P. Moussalem
Also CEA-N-2426
NEACRP-A- 697
Summary Record of the 6th Meeting of the Scientific
Co-ordination
Group of the Joint Evaluated File Project, 14th-15th
February 1985,
Paris
Also JEF/DOC-90, NEANDC-A-199
NEACRP-A- 698
Summary Record of a NEACRP Restricted Specialists' Meeting
on the
Intercomparison of methods for calculating shielded Cross
Sections
in the Unresolved Resonance Region, Santa Fe, 15th May
1985.
NEACRP-A- 699
State of the Art on Reactor Noise Analysis
P. Bernard, D. Fry, D. Stegemann, H. van Dam
NEACRP-A- 700
NEA Data Bank Activity Report, November 1985.
NEACRP-A- 701
A Glance at NEA's Programme of Work in the Nuclear Safety
Area
NEACRP-A- 702
CJD Activities in 1983-1985
V.N. Manokhin et al.
NEACRP-A- 703
Status Review of the High Priority Request List (September
1983 issue).
NEACRP-A- 704
A Method for the Determination of Albedos for Nuclear
Reactor Codes.
O. Norinder
NEACRP-A- 705
Three-Dimensional Multi-Group Neutron Transport
Calculations by Double
Finite
Element Method.
T. Fujimura, Y. Nakahara and M. Obara
NEACRP-A- 706
BERMUDA-3DN: A Three-Dimensional Neutron Transport Code in
(x,y,z)
Geometry
T. Susuki, A. Hasegawa and T. Ise.
NEACRP-A- 707
Development of a Radiation Transport Code in the
Three-Dimensional
(x,y,z)
Geometry for Shielding Analysis
T. Ida, Y. Oka, S. Kondo and Y. Togo.
NEACRP-A- 708
Three-Dimensional Transport Calculation Method for
Eigenvalue Problems
using
Diffusion Synthetic Acceleration
M. Bando, T. Yamomoto, Y. Saito, T. Takeda
NEACRP-A- 709
Discrete Ordinates Transport Code in Hexagonal-Z Geometry.
Y. Saito, M. Bando, T. Takeda
NEACRP-A- 710
Three-Dimensional Transport Correction in Fast Reactor
Core Analysis
T. Takeda, Y. Sasaki, Y. Saito
NEACRP-A- 711
Recent Developments of the Transport Theory Code MARC/PN
J.K. Fletcher
NEACRP-A- 712
BISTRO A Fast Two-dimension SN Transport Code for Keff
Calculations
C.J. Gho, G. Palmiotti, J.M. Rieunier, M. Salvatores
NEACRP-A- 713
Spatial Kinetics Effects on Reactivity Measurements in ZPPR
S.G. Carpenter, S.B. Brumbach, R.W. Goin
NEACRP-A- 714
Some Methods of Taking in Account Spatial Effects at
Reactivity Measurement
Yu.A. Kazansky, V.A. Lititsky, I.P. Matveenko, A.G.
Shokodko
NEACRP-A- 715
252CR-Source-Driven Neutron Noise Analysis Method
J.T. Mihalczo, W.T. King, E.D. Blakeman
NEACRP-A- 716
Control Cluster Efficiency Measurements in PWRs by
Analysing Power Signals during a Rod Drop
J. Cray
NEACRP-A- 717
Some Evidence of Space Kinetics Effects in Rod-Drop
Experiments at Masurca
J.P. West, J.C. Gauthier
NEACRP-A- 718
Local Heterogeneity Effects on Small Sample Worths
R.W. Schaefer
NEACRP-A- 719
Experimental Study of Large Scale Axially Heterogeneous
LMFBR Core at FCA Assembly XIII-1
S. Iijima, S. Okajima, T. Sanda, M. Obu, T. Koakutsu, T.
Hayase
NEACRP-A- 720
A Method to Take in Account Control-Rod Heterogeneity
Effects
G. Palmiotti, D. Riou
NEACRP-A- 721
Effective Beta Measurements on Uranium and Plutonium Fast
Reactor Mockups
E.F. Bennett and R.W. Schaefer
NEACRP-A- 722
Beam Port Detector Response Calculations for the R2 Reactor
R.M. Lell
NEACRP-A- 723
The State of CADENZA and ZPPR-12 Analysis
P.J. Collins
NEACRP-A- 724
Prediction of K-Effective and Leakage for Dimple Assembly
SO3/20/A using theMonte Carlo Computer Code MONK
A.F. Course
NEACRP-A- 725
Further Studies of the Prescott Interaction Problem using
Superstage Powering in MONK 6.4
R.J. Brissenden, N.R. Smith
NEACRP-A- 726
A Review of Lattice Calculations for the PROTEUS-LWHCR
Phase I Experiments
R. Chawla
NEACRP-A- 727
A Generalized Dancoff Factor for Application to HCPWR in
Complex Lattice Arrangement
Y. Ishiguro, K. Kaneko
NEACRP-A- 728
The Study for the Control Rod Worth in High Conversion PWR
E. Saji, A Takahashi, S. Uchida, K. Suzuki
NEACRP-A- 729
Experimental Program and Results of Pre-analysis for a
High Conversion Light Water Reactor (HCLWR) at FCA
T. Osugi, H. Yoshida
NEACRP-A- 730
Le Programme Experimental de Neutronique pour les
Reacteurs a Eau Avances
L. Martin-Deidier, S. Cathalau, A. Santamarina, M. Gomit
NEACRP-A- 731
Tests of a Reactor Physics Calculational Model against
Measured Results for Tight LWR Lattices
E. Johansson
NEACRP-A- 732
A Next Generation Steady State Neutron Source
R.M. Moon, C.D. West
NEACRP-A- 733
On the Neutronics of SINQ, a Continuous Spallation Neutron
Source
W.E. Fischer
NEACRP-A- 734
IPNS Booster Target Neutronics Design Work
R.N. Blomquist
NEACRP-A- 735
Neutronics Study on Blanket System of High Tritium
Breeding Ratio
S. Mori, Y. Seki
NEACRP-A- 736
A Cross-Section Sensitivity and Uncertainty Analysis on
Fusion Reactor Blankets with SAD/SED Effect
K. Furuta, Y. Oka, S. Kondo
NEACRP-A- 737
Integral Experiments in a 120-CM Lithium Sphere
K. Sugiyama, K. Kanda, S. Iwasaki, M. Nakazawa, H.
Hashikura, H. Sekimoto, T. Iguchi, S. Itoh, K. Sumita, A. Takahashi, J.
Yamamoto
NEACRP-A- 738
Clean Benchmark Experiments and Analyses at FNS
H. Maekawa
NEACRP-A- 739
Activation Calculations for NET III A and FCTR
C. Ponti
NEACRP-A- 740
Some Remarks on the Feedback Coefficients at Phenix
P. Coulon
NEACRP-A- 741
Fusion Blanket Experiments
T.J. Yule
NEACRP-A- 742
Core Design and Performance of Small Inherently Safe LMRs
Y. Orechwa, H. Khalil, E.K. Fujita, R.B. Turski
NEACRP-A- 743
Fuel Management Studies of Small Metal and Oxide LMR's
H. Khalil, E.K. Fujita, S. Yang, Y. Orechwa
NEACRP-A- 744
Characteristics of Plutonium Utilization in ATR
T. Wakabayashi, N. Tukumura, N. Aihara, S. Ohteru
NEACRP-A- 745
Plutonium Recycling in the French PWRs
NEACRP-A- 746
Burnup Characteristics of JOYO MK-II Core
T, Ikegami, N. Mizoo
NEACRP-A- 747
The Reactivity History of PFR during Period 1975 to 1984
D.J. Lord
NEACRP-A- 748
Uncertainties and Model Improvements for the Definition of
a Lumped Fission Product for LMFBR Design Calculations
N. Karouby-Cohen
NEACRP-A- 749
Status of Reaction Rate Calibrations at ZPPR
S.G. Carpenter
NEACRP-A- 750
Intercomparison of Reaction Rate Measurement Techniques in
MASURCA
W. Scholtyssek, G. Granget
NEACRP-A- 751
TMI-2 Criticality Studies: Lower-Vessel Rubble and
Analytical Benchmarking
R.M. Westfall, J.R. Knight, P.B. Fox, O.W. Hermann, J.C.
Turner
NEACRP-A- 752
NEACRP Statement on the Status Review of the High Priority
Request List
NEACRP-A- 753
Committee Summary Record of 28th Meeting of NEACRP,
Madrid, 2nd - 6th November
1985 (also NEANDC-A-208)
NEACRP-A- 754
NEA Summary Record of 28th Meeting of NEACRP, Madrid, 2nd
to 6th November
1985 SEN/NEACRP/M(85)2 (Also NEANDC-A-221)
NEACRP-A- 755
Committee Summary Record of 25th NEANDC Meeting,
Paris/Grenoble, 18th - 22nd November 1985
(Also NEANDC-A-219)
NEACRP-A- 756
NEA Summary Record of 25th Meeting NEANDC, Paris/Grenoble
18th-22nd November 1985 SEN/NEANDC/M(85)1
(Also NEANDC-A-220)
NEACRP-A- 757
IAEA MEETINGS
NEACRP-A- 758
Summary Record of the 7th Meeting of the JEF Scientific
Coordination Group.
Also NEANDC-A-223
NEACRP-A- 759
A proposed NEACRP/NEADB Reactor Physics Data Base and
Validation System
September 1986
NEA Data Bank
NEACRP-A- 760
NEA Data Bank Activity Report, September 1986
NEACRP-A- 761
Summary report of the 19th Annual Meeting of IWGFR
Kalpakkam, India, 11-14 March 1986
NEACRP-A- 762
Report by the Secretariat on Recent Activities of the
Committee on the Safety of Nuclear Installations of interest to NEACRP
Also as SINDOC(86)148
NEACRP-A- 763
IAEA Activities of potential interest to the NEACRP
NEACRP-A- 764
Evaluation of Delayed Neutron Data for Thermal Fission of
U-235 Based on Integral Experiments using SHE
Y. Kaneko, F. Akino, T. Yamane
NEACRP-A- 765
Status of Evaluated Precursor and Aggregate Spectrum
T.England, et al.
NEACRP-A- 766
Some Investigations on the Reactivity Scale for the
Super-Phenix Start Up Experiment Analysis
A. D'Angelo, B. Vuillemin, J.C. Cabrillat
NEACRP-A- 767
Comparison of WIMS Predictons with Reactivity Measurements
made on Samples of Irradiated DRAGON Fuel in the HECTOR reactor
J. Marshall, J.L. Hutton
NEACRP-A- 768
Fission-Product Yield Data for the US/UK Joint Experiment
in the Dounreay Prototype Fast Reactor
J.K. Dickens, S. Raman
NEACRP-A- 769
Integral-Data Test of JEF-1 Fission-Product Cross Sections
A.J. Jansson, et al.
NEACRP-A- 770
An Investigation of Neutron Absorption by Fission Products
using the Reactivity Perturbation Method
S.M. Bednyakov
NEACRP-A- 771
System Dynamics Analysis for Mitigating ATWS Consequences
of a 1000 MWe Loop-Type LMFBR
K. Yamaguchi, H. Endo
NEACRP-A- 772
LMR Core Design for Inherent Safety
D.C. Wade
NEACRP-A- 773
Implications of the EBR-II Inherent Safety Demonstration
Test
H.P. Planchon, et al.
NEACRP-A- 774
The ZPPR-15A IFR Critical Experiments Program: Early
Results from a Pu/U Metal Fuel Core Simulation
NEACRP-A- 775
Improved Locations of Reactivity Devices in Future CANDU
Reactors Fuelled with Natural Uranium or Enriched Fuels
P.G. Boczar, M.T. van Dyk
NEACRP-A- 776
A Coarse Mesh 3-D Transport Calculation Code with
Diffusion Synthetic Acceleration
H. Sakuma, N. Ito, T. Takeda
NEACRP-A- 777
Review of Application and Improvement of a
Three-Dimensional Discrete Ordinates Transport Code ENSEMBLE
T. Nishimura, et al.
NEACRP-A- 778
Three-Dimensional Oak Ridge Transport Code (TORT)
NEACRP-A- 779
RITME: A Fast Computing Simulator for 3-D Power
Distribution Calculations in Large PWR Cores
P. Bernard, et al.,
NEACRP-A- 780
EAC: The Modular European Accident Code for LMFBR Safety
Analysis
G. Van Goethem, et al.
NEACRP-A- 781
Method of Characteristics in the Regions with Complex
Geometry
J.R. Suslov
NEACRP-A- 782
Spatial Kinetics Effects in Reactivity Measurements in ZPPR
S.G. Carpenter, S.B. Brumbach, R.W. Goin
NEACRP-A- 783
Taking Account of Spatial Effects in Reactivity
Measurement by the Inverse Kinetics Method
V.A. Lititsky, I.P. Matveenko, A.G. Shokodko
NEACRP-A- 784
The Enhancement of Control Rod Worths in Fast Rectors by
the Introduction of Moderators
G. Ingram, M.J. Grimstone
NEACRP-A- 785
Experimental Study of Large Scale Axially Heterogeneous
LMFBR Core at FCA Assembly XIII
S. Iijima, et al.
NEACRP-A- 786
Two Dimensional Cell Heterogeneity Effect in Analysis of
Fast Critical Assemblies
T. Takeda, et al.
NEACRP-A- 787
Parametric Experiments on Control Rod Heterogeneity in the
Framework of the BALZAC Program
Y.C. Kim, et al.
NEACRP-A- 788
Measurements and Calculations of B-10 (n,He) and U-235
(n,f) Reaction Rates in a Control Rod Mock-up in ZPPR
S.B. Brumbach, et al.
NEACRP-A- 789
Breeding Characteristics of Fast Sodium Reactors with
Heterogeneous Core
P.N. Alekseev
NEACRP-A- 790
Summary of Recent Results from the JAERI/US Fusion
Neutronics Phase I Experiments
T. Nakamura, M.K. Abdou
NEACRP-A- 791
Measured Neutron Parameters for Phase I Experiments at the
FNS Facility
H. Maekawa, et al.
NEACRP-A- 792
Neutronics Experiments in a Li-Pb Spherical Assembly
K. Sugiyama, et al.
NEACRP-A- 793
First Results of LBM Experiment at Lotus and its Analysis
P.A. Haldy, J. Stepanek
NEACRP-A- 794
Neutron Flux Measurements for the Lithium-Tritium Sweep
Gas Tests
E.F. Bennett, T.J. Yule
NEACRP-A- 795
Neutron Flux Measurements for the Lithium-Tritium Sweep
Gas Tests
R.E. Donders, et al.
NEACRP-A- 796
Analysis of Nuclear Characteristics of Chernobyl Reactor
by WIMS-ATR Code
T. Wakabayashi, N. Fukumura
NEACRP-A- 797
Initial Critical Experiments in FCA-HCLW Core
T. Osugi, et al.
NEACRP-A- 798
Proposal of Benchmarks on Data and Method to Calculate
Reactor Characteristics in High Conversion Light Water Reactors
Y. Ishiguro, H. Akie, H. Takano
NEACRP-A- 799
Sensitivity Analysis of Cell Parameters in High-Conversion
Light Water Reactors
M. Nakano, T. Takeda, H. Takano
NEACRP-A- 800
Computational Breakdown of the HCLWR Infinite Lattice Void
Reactivity into Contributing Nuclides and Energy Groups
K. Nishina, K. Okumura
NEACRP-A- 801
Validation of HELIOS.HX Code for HCLWR Lattice Analysis
Y. Yamamoto, et al.
NEACRP-A- 802
The Effect of Fission Products on Burn-Up Characteristics
in High Conversion Light Water Reactors
H. Takano, H. Akie, Y. Ishiguro
NEACRP-A- 803
Special ZPPR Experiments on Sodium Manometer Worth and
Core Axial Expansion Worth
NEACRP-A- 804
Development of the Traditional Group Diffusion Method on
to a Correct Representation of Bilinear Functionals
M.F. Vorotynstev, A.A. Rineysky
NEACRP-A- 805
A Data Base System for Reactor Physics Experiments at the
Critical Assembly of Kyoto University
C. Ichihara
NEACRP-A- 806
A Computer Code System for Integral Experiment Data Bank
Y. Naito
NEACRP-A- 807
Critical (Integral) Experiment Data Banking: ZPPR
Perspective
L.G. LeSage
NEACRP-A- 808
Verification of BNAB-78 Constants Set by the Basis of
Integral Experiment Data Bank
A.M. Taybulya, et al.
NEACRP-A- 809
BDI: The Cadarache Data Bank for LMFBR Integral Experiment
Data
G. Rimpault, G. Reynaud
NEACRP-A- 810
Status Report: OECD-NEACRP Working Group on Criticality
Calculations
G.E. Whitesides
NEACRP-A- 811
Intercomparison of Cross-Section Libraries used for Spent
Fuel Caskm Shielding Analyses
C.V. Parks, et al.
NEACRP-A- 812
SHETAN Calculation of a Cruciform Absorber Benchmark
F.C. Wong, J.D. Irish
NEACRP-A- 813
SEN/NEACRP/M(86)2 (also NEANDC- A) Summary Record of 29th
Meeting of NEACRP Committee, Chalk River
NEACRP-A- 814
Also NEANDC- A : Summary Record (Blue cover) of 29th
Meeting of NEACRP in Chalk River, Canada
Compiled by J.M. Stephenson
NEACRP-A- 815
Call for papers - Specialist Meeting on Data for Decay
Heat Predictions
NEACRP-A- 816
Survey on manpower available in the field of Nuclear Data
for Applications In OECD countries. 1985
K. Boeckhoff and C. Buerkholz
816bis sent by author on 19.9.88
NEACRP-A- 817
Summary Record of the 8th JEF scientific coordination group
NEACRP-A- 818
List of CSNI International Standard Problems
Nuclear Energy Agency
August 1987
NEACRP-A- 819
Reproduction and Distribution of the Documents of the
NEACRP
NEACRP Secretariat
1987
NEACRP-A- 820
Steering Committee for Nuclear Energy: Renewal of the
Mandate of the NEACRP Terms of Reference
Nuclear Energy Agency
1987
NEACRP-A- 821
NEA Data Bank Activity Report 1986 - 1987
NEA Data Bank
September 1987
NEACRP-A- 822
Report by the Secretariat on Recent Activities of the CSNI
of Interest to the Committee on Reactor Physics
Nuclear Energy Agency CSNI Secretariat
September 1987
NEACRP-A- 823
Summary of the NEACRP Specialist Meeting on Shielding
Benchmarks
OECD, Paris, 13-14th October 1986
NEACRP Secretariat
Paris 13-14 October 1986
NEACRP-A- 824
Report on Relevant IAEA Activities to the NEACRP.
IAEA
September 1987
NEACRP-A- 825
Analysis of the Chernobyl Reactor Accident (I). Nuclear
and Thermal Hydraulic Characteristics and Follow-up Calculation
of Accident. PNC.
T. Wakabayashi et Al.
September 1987
NEACRP-A- 826
Analysis of the Chernobyl Reactor Accident (II). An
Examination of the Improvement Measures concerning the Accident of
Chernobyl Power Plant.
PNC.
T. Wakabayashi et Al.
September 1987
NEACRP-A- 827
An Analysis of Reactivity Coefficients of the Chernobyl
Reactor by Cell Calculation. JAERI.
K. Tsuchihashi, F. Akino
September 1987
NEACRP-A- 828
Measurements of Void Reactivity Effects in CIRENE Mock-up
Fuel Channels At RB-3. ENEA.
A. Grossi, A. Vanossi
September 1987
NEACRP-A- 829
A Guide to the Use of "KENO-EUR" A Code for Perturbation
Analysis in Multiplying Systems. JRC.
H. Rief
July 1987
NEACRP-A- 830
An Assessment of Lattice Characteristics that Influence
Coolant Void Reactivity in CANDU-type Lattices. AECL.
J. Griffiths, P.G. Boczar, M.T. van Dyk
August 1987
NEACRP-A- 831
The Chernobyl Accident. Multidimensional Simulations to
Identify the Role of Design and Operational Features of the RBMK-1000.
AECL.
P.S.W. Chan et Al.
August 1987
NEACRP-A- 832
Review of Prototype Fast Reactor (PFR) Reactivity Feedback
Coefficient Measurements 1974-1978. UKAEA.
D.J. Lord et Al.
June 1987
NEACRP-A- 833
Uncertainty Analysis on the Measurement and Calculation of
Feedback Effects in LMFBR. Application of SUPER-PHENIX-1 Start-Up
Experiments
CEA.
P. Bergeonneau, M. Salvatores, M. Vanier
August 1987
NEACRP-A- 834
A Simplified Analysis of Uncertainty Propagation in
Inherently Controlled ATWS Events. ANL.
D.C. Wade
September 1987
NEACRP-A- 835
Uncertainties in Coefficients of Reactivity of the BN-Type
Fast Reactors. Obninsk.
I.A. Kuznetsov, I.P. Matveenko
September 1987
NEACRP-A- 836
On the Reactivity Effects of Nuclear Fuel Fragmentation
with Reference to the Chernobyl Accident. VTT.
F. Wasastjerna
September 1987
NEACRP-A- 837
Integral Experiment Analysis on Refinement of Rhodium-103
and Palladium-105 Capture Cross-Sections in Fast Critical Assemblies.
USSR.
S.M. Bednyakov
September 1987
NEACRP-A- 838
Analysis of Experiments on Critical Assemblies for Testing
the Constant Support of Reactor Calculations. USSR.
E.A. Gomin et Al.
September 1987
NEACRP-A- 839
The Concept of Fast Sodium Power Reactor with In-Assembly
Heterogeneity.
Kurchatov Institute.
V.V. Orlov et Al.
September 1987
NEACRP-A- 840
Comparison Between Calculated and Experimental Effective
Beta Results on ZPPR and SNEAK Fast Facilities. ENEA/CEA.
A. D'Angelo, M. Salvatores
August 1987
NEACRP-A- 841
Calculation of Integrated Characteristics of Delayed
Neutrons. USSR.
L.G. Manevich et Al.
September 1987
NEACRP-A- 842
Neutronic Experimental Program in France for the
Qualification of Unmoderated PWR Calculation. CEA
M. Darrouzet et Al.
September 1987
NEACRP-A- 843
Results and Analyses for FCA Phase-1 Experiment on High
Conversion Light Water Reactor. JAERI.
T. Osugi et Al.
September 1987
NEACRP-A- 844
Some Special Methodical and Nuclear Data Investigations
for Tight Lattice PWR-Cores (HCLWR and PROTEUS). KFK.
C.H.M. Broeders, A. Mateeva, H. Kuesters
September 1987
NEACRP-A- 845
Uncertainty Evaluation of Void Reactivity Worth in High
Conversion Light Water Reactors. Osaka University.
Y. Yamaguchi, T. Takeda
September 1987
NEACRP-A- 846
Investigation of the Void Coefficient and Other Integral
Parameters in the PROTEUS-LWHCR Phase II Programme. EIR/KWU/KFK.
R. Seiler et Al.
September 1987
NEACRP-A- 847
Amelioration de la Connaissance de la Capture des Produits
de Fission dans les Reacteurs a Eau. CEA.
L. Martin-Deidier, J. Krebs
September 1987
NEACRP-A- 848
Recent Data and Method Improvements for the Pseudo-Fission
Product Cross-Sections Assessment in a LMFBR. CEA.
L. Martin-Deidier, M. Salvatores
August 1987
NEACRP-A- 849
Preliminary Report of HCLWR Cell Burn-up Benchmark
Calculations. JAERI.
H. Akie, Y. Ishiguro, H. Takano
September 1987
NEACRP-A- 850
CEA Contribution to the HCLWR Burn-up Benchmark Proposed
by NEACRP. CEA.
P. Chaucheprat
September 1987 (Revision December 1987)
NEACRP-A- 851
EIR Results for the HCLWR NEACRP Burn-up Benchmark
Obtained using EIR Version of DANDE System and JEF Library. EIR.
J. Stepanek and P. Vontobel
September 1987
NEACRP-A- 852
Inherent Safety Performance of a Mixed-Oxide-Fueled 1000
MWe Loop-Type LMFBR under ATWS Conditions. PNC/NAIG/Toshiba.
K. Yamaguchi, S. Ohta, H. Endo
September 1987
NEACRP-A- 853
Trends vs Reactor Size of Passive Reactivity Shutdown and
Control Performance. ANL.
D.C. Wade, E.K. Fujita
September 1987
NEACRP-A- 854
A Simplified Model of Core Thermal Dilation. ANL.
T.J. Moran
September 1987
NEACRP-A- 855
A Technique for Computing Bowing Reactivity Feedback in
LMFBR's. ANL.
P.J. Finck
September 1987
NEACRP-A- 856
Optimisation of Reactivity Effects in Fast Reactors.
Kurchatov Institute.
P.N. Alekseev, I.S. Slesarev, M.V. Trunov
September 1987
NEACRP-A- 857
Fusion Blanket Engineering Benchmark Experiments -
JAERI/USDOE Collaborative Program Phase II. JAERI/USDOE.
T. Makamura
September 1987
NEACRP-A- 858
Error and Uncertainty Analysis of Neutron Transport
Calculation. University of Tokyo.
K. Furuta, Y. Oka, S. Kondo
September 1987
NEACRP-A- 859
On the Proposal of International Comparison of the
Measuring Techniques for Tritium Production Rate Used for Fusion
Neutronics Experiment. FRPL.
Y. Kaneko, T. Nakamura, H. Maekawa
September 1987
NEACRP-A- 860
Neutron Spectrum Measurements with Proton Recoil Counters
at FNS. ANL.
E.F. Bennett
September 1987
NEACRP-A- 861
Simulation of Detailed Space - Energy Distribution of
Neutrons in Intermediate Reactors. Kurchatov Institute.
A.G. Morozov, I.S. Slesarev
September 1987
NEACRP-A- 862
EURACOS Iron and Sodium Benchmark Analysis. A Comparison
of JEF-1 and BMCCS In Cross-Sections in Cross-Sections in Deep
Penetration Experiments. JRC.
September 1987
NEACRP-A- 863
Draft Report on Criticality Benchmarks (and Memo). ORNL
G.E. Whitesides
September 1987
NEACRP-A- 864
Summary of the Second Meeting on the NEACRP
Intercomparison of Codes for the Shielding Assessment of Transportation
Packages. AEE Winfrith.
A. Avery
September 1987
NEACRP-A- 865
Status of IRMA. ANL.
S.G. Carpenter
September 1987
NEACRP-A- 866
Thermal Fission Product Benchmarks. AEE Winfrith.
M.J. Halsall
September 1987
NEACRP-A- 867
C.E.A. Contribution to the Thermal Fission Product
Benchmark Proposed by NEACRP. CEA.
P. Chaucheprat
September 1987
NEACRP-A- 868
The Third Meeting on the Status of Reactor Physics in the
Nordic Countries.
VTT.
September 1987
NEACRP-A- 869
Application of Critical Experiments and Operating Data to
Core Design in Formal Measurements of Cross-Section Data Adjustment.
ANL.
Proposal Specialists Meeting
September 1987
NEACRP-A- 870
Future Management of the WIMS Group of Codes at Winfrith.
AEE Winfrith.
September 1987
NEACRP-A- 871
Summary Record of the 30th NEACRP Meeting held at Helsinki
from 14th to 18th September 1987.
NEANDC-A-244
J.M. Stevenson
September 1987
NEACRP-A- 873
Summary Record of the 26th NEANDC Meeting held at Rome
from 18th to 22th May 1987. SEN/NEANDC/M(87)1
May 1987
NEACRP-A- 874
Summary on SMORN-V
Munich, October 12-18, 1987.
W. Bastl
30 October 1987
NEACRP-A- 875
Specialists' Meeting on the NEACRP Burnup Benchmark
Calculations for High Conversion Light Water Reactor Lattices. Paris,
18-22 April 1988.
First Circular
Y. Ishiguro , E. Sartori
17 December 1987
NEACRP-A- 876
Specialists' Meeting on the Application of Critical
Experiments and Operating Data to Core Design via Formal Methods of
Cross Section Data Adjustment. Jackson Hole, 23-24 September 1988.
First Circular
D. C. Wade
5 April 1988
NEACRP-A- 877
NEACRP Criticality Working Group Meeting, 28-30 June 1988
First Circular
NEACRP Secretariat
16 May 1988
NEACRP-A- 878
Summary Record of the Ninth Meeting of the Scientific
Coordination Group of the Joint Evaluated File Project.
JEF Secretariat
Paris 14 April 1988
NEACRP-A- 879
International Comparison of Tritium Production Rate
Measurements for Fusion Neutronics Research.
Y. Kaneko, T. Nakamura
June 1988
NEACRP-A- 880
A Glance at NEA's Programme of Work in the Nuclear Safety
Area.
CSNI Secretariat
June 1988
NEACRP-A- 881
Proposal of 3-D Neutron Transport Benchmark Problems
T. Takeda M. Tamitani and H. Unesaki
Draft, September 1988
NEACRP-A- 882
Reduction of Void Reactivity in Light Water Cooled, Heavy
Water Reactors
R. Martinelli, A.R. Dastur, H.C. Chow
ENEA Roma
Session 2.6 - 31st NEACRP Meeting O-arai
NEACRP-A- 883
Summary of "Specialists' Meeting on In-core
Instrumentation and Reactor Core Assessment", Cadarache, France, June
1988
R. Martinelli, ENEA
Chairman Summary unavailable at the time of 31st NEACRP
Meeting
NEACRP-A- 884
Shielding Experimental Benchmark Data Base at the Nuclear
Energy Agency Data Bank.
7th International Conference on Radiation Shielding,
Bournemouth,
12-16 September 1988
P. Miller, P. Nagel, M. Salvatores, E. Sartori
NEACRP-A- 885
Progress Report from NEA Data Bank, October 1988
NEACRP Secretariat
31st NEACRP; Session A 5
NEACRP-A- 886
Overview of the IAEA Reactor Physics Activities, September
1988
M. Crijns
31st NEACRP : Session A 5.
NEACRP-A- 887
Fast Breeder Reactor Advanced Core Studies in France
October 1988
J. Ravier, J. Berthet, H. Sztark
Session B 1.1 - 31st NEACRP Meeting
NEACRP-A- 888
A Limited Survey of the Gamma-Heating Measurements and
their Role in Validating the French LMFBR Calculational Methods and
Data During the Period 1982-1990
D. Calamand, CEA Cadarache
Session B 1.3 - 31st NEACRP Meeting
NEACRP-A- 889
Prompt Gammas Emitted in Fission
October 1988
E. Fort, J. Frehaut, P. Long
Session B 1.3 - 31st NEACRP Meeting
NEACRP-A- 890
Analysis of a Control-Rod Ejection Transient in a
Mox-Fuelled PWR
October 1988
M. Lam Hime, R. Lenain, G. Mathonniere, J.P. Perrutel, M.
Rohart, H. Schaeffer, S. Stelletta
Session B 1.4 - 31st NEACRP Meeting
NEACRP-A- 891
MORGANE/S : Fission Product Capture Measurements in a
HCLWR Tight Lattice
October 1988
J. Mondot, J.M. Gomit, C. Garzenne, P. Chaucheprat, A.
Santamarina
Session B 2.3 - 31st NEACRP Meeting
NEACRP-A- 892
SUPER-PHENIX Effective Beta : Calculated Values Comparison
October 1988
A. D'Angelo
Session 2.4 - 31st NEACRP Meeting
NEACRP-A- 893
Investigations of an Advanced Reactor With Pu Fuel
Controlled without Soluble Boron
October 1988
J. Bergeron, R. Lenain
Session B 2.5 - 31st NEACRP Meeting
NEACRP-A- 894
IRMA : Interlaboratory Comparison of Fission and Capture
Rate Measurement Techniques at MASURCA
W. Scholtyssek, M. Angelone, P. D'Hondt, G. Granget,
B.L.H. Burbridge, K. Gmuer, D. Maddison, P. Marimbeau
Session B 4.5 - 31st NEACRP Meeting - also NEACRP-L-315
NEACRP-A- 895
Progress with the NEACRP Intercomparison of Codes for the
Shielding Assessment of Transportation Packages. October 1988
A. Avery
Session B 4.3 : 31st NEACRP Meeting
NEACRP-A- 896
Preliminary Study on the Feasibility of Ductless Fuel
Assembly for Fast Reactors. October 1988
I. Shibahara and Y. Enokido
Session B 1.1 : 31st NEACRP Meeting
NEACRP-A- 897
A High Breeding Fast Reactor With a New Concept of
Metallic Fuel Assemblies.
Int. Reactor Physics Conf. 88, Jackson Hole
T. Hiraoka, K. Sako, H. Takano, M. Osakabe
Session B 1.1 : 31st NEACRP Meeting
NEACRP-A- 898
Analysis of the Partial-Refueling Type Ultra Long Life
Core Using Metallic Fuels for 1000 MWe-LMFBRs. October 1988
K. Kawashima and R.A. Karam
Session B 1.1 : 31st NEACRP Meeting
NEACRP-A- 899
Assessment of LMFBR Core Design Concepts Using Metallic
Fuels
Int. Reactor Physics Conf. 88, Jackson Hole
T. Nishimura, Y. Yokoo, Y. Tanaka, K. Kawashima, I.
Kakehi, M. Kawashima,, T. Hojuyama
Session B 1.1 : 31st NEACRP Meeting
NEACRP-A- 900
Transmutation of Transuranic Wastes by Proton-induced
Nuclear Spallation Reactions, October 1988
T. Nishida, Y. Nakahara, I. Kanno, H. Takada, Y. Kaneko
Session B 1.2 : 31st NEACRP Meeting
NEACRP-A- 901
Conceptual Study of Actinide Burner Reactors
Int. Reactor Physics Conf. 88, Jackson Hole
T. Mukaiyama, H. Takano, T. Takizuka, T. Ogawa, M. Osakabe
Session B 1.2 : 31st NEACRP Meeting
NEACRP-A- 902
Analysis of ZPPR-17A Gamma Heating Experiments
October 1988
H. Unesaki and P.J. Collins
Session B 1.3 : 31st NEACRP Meeting
NEACRP-A- 903
On the Passive Safety of OTTO and Multipass Fuel Cycles of
Modular High Temperature Reactor and Concept of Fuel Discharge Safe
Reactor.
October 1988
H. Sekimoto, P.H. Liem, Y.H. Rose, E. Suetomi
Session B 2.1 : 31st NEACRP Meeting
NEACRP-A- 904
Measurement of Feedback Reactivity of Experimental Fast
Reactor JOYO.
October 1988
T. Aoyama, Y. Arii, N. Mizoo
Session B 2.1 : 31st NEACRP Meeting
NEACRP-A- 905
The Concept of High Conversion Light Water Reactor with
Flat Core and its Applications.
Int. Reactor Physics Conf. 88, Jackson Hole
Y. Ishiguro, K. Okumura, H. Akie, T. Mori, H. Takano
Session B 2.5 : 31st NEACRP Meeting
NEACRP-A- 906
Reactor Physics Experiments on High Conversion Light Water
Reactor at Plutonium Fueled FCA-XV 1 Core.
Int. Reactor Physics Conf. 88, Jackson Hole
T. Osugi, S. Okajima, M. Obu, T. Sakurai
Session B 2.5 : 31st NEACRP Meeting
NEACRP-A- 907
The Sensitivity of Coolant Void Reactivity at High Voidage
for Tight Pitch Lattice. October 1988
Y. Yamaguchi and T. Takeda
Session B 2.5 : 31st NEACRP Meeting
NEACRP-A- 908
Study on Coolant Void Reactivity of Pressure Tube Type
Heavy Water Lattice by Substitution Method.
Nucl. Sci. and Eng. 1988
Y. Kowata and N. Fukumura
Session B 2.6 : 31st NEACRP Meeting
NEACRP-A- 909
Proposal of International Comparison on Measuring
Techniques of Tritium Production Rate for Fusion Neutronics Experiment.
October 1988 (Revision of NEACRP-A-859)
T. Nakamura, H. Maekawa and P. Haldi
Session B 4.8 : 31st NEACRP Meeting
NEACRP-A- 910
Actinide Transmutation by Spallation in the Light of
Recent Cyclotron Development
P. Bonnaure, H. Rief, P. Mandrillon, H. Takahashi
Session B 1.2 : 31st NEACRP Meeting
NEACRP-A- 911
Nuclear Transmutation of Radioactive Waste: A Review of
the State of the Art
E. Schmidt
Session B 1.2 : 31st NEACRP Meeting
NEACRP-A- 912
Review of Actinide Monitoring at the JRC - Ispra
W. Hage
Session B 1.5 : 31st NEACRP Meeting
NEACRP-A- 913
Some Applications of Stochastic Processes in Neutron
Coincidence Measurements used in Nuclear Safeguards
W. Matthes
Session B 1.5 : 31st NEACRP Meeting
NEACRP-A- 914
Feasibility Studies of Passive Safeguards Interrogation of
Irradiated Fuel Containers.
Y. Yeivin, H. Rief, G. Gonano, R. Van Heusden
Session B 1.5 : 31st NEACRP Meeting
NEACRP-A- 915
Construction of a Neutron Deep Penetration Sodium Shield
Mock-up
G. Perlini, S. Acerbis, U. Canali, G. Gonano, R. Nicks, H.
Rief
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 916
Neutronic Spectrometry Measurements in Sodium
G. Perlini, S. Acerbis
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 917
Neutron Spectrometry Measurements in Iron
G. Perlini, M. Carter, S. Acerbis
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 918
Fission Neutron Penetration in Iron and Sodium.
Part I: Activation Measurements
R. Nicks, G. Perlini, H. Rief
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 919
Fission Neutron Penetration in Iron and Sodium.
Part II: Neutron Spectrometry
R. Nicks, G. Perlini, H. Rief
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 920
Interpretation of EURACOS Iron and Sodium Benchmarks
G. Perlini, H. Rief, E. Vittone, K. Burn
Session B 4.1 : 31st NEACRP Meeting
NEACRP-A- 921
Thermal Fission Product Benchmark.
October 1988
M.J. Halsall, C.J. Taubman
Session B 4.6 : 31st NEACRP Meeting
NEACRP-A- 922
Experiments and Analysis for an Axially Heterogeneous LMR
Assembly at ZPPR.
P.J. Collins, S.B. Brumbach
Session B 1.1 : 31st NEACRP Meeting
NEACRP-A- 923
Physics Studies of Higher Actinide Consumption in an LMR.
R.N. Hill
Session B 1.2 : 31st NEACRP Meeting
NEACRP-A- 924
Analysis of Gamma Ray Heating Measurements in ZPPR-17A.
P.J. Collins and H. Unesaki
Session B 1.3 : 31st NEACRP Meeting
NEACRP-A- 925
Limitations of Nondestructive Analysis.
P.J. Persiani
Session B 1.5 : 31st NEACRP Meeting
NEACRP-A- 926
Status of Radiation Damage Studies in the US LMR Program.
Y. Orechwa
Session B 1.7 : 31st NEACRP Meeting
NEACRP-A- 927
Radial Expansion Feedback in LMR's: an Assessment of
Neutronic Approximations.
Int. Rea
