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IAEA1420 ZZ-ADS-LIB/V1.0. (Abstract last modified 13-FEB-2008)
1.
NAME OR DESIGNATION - ZZ-ADS-LIB/V1.0. 2.
COMPUTER FOR WHICH THIS PACKAGE IS DESIGNED -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
IAEA1420/01 IBM PC,PC Windows PC Windows
3.
DESCRIPTION - 4.
METHODS - Processing was carried out using NJOY-99.90 with the local updates at IAEA-NDS. The resulting processed files are available in ACE format for Monte Carlo transport calculations and in MATXS format for deterministic transport calculations. 6.
TYPICAL RUNNING TIME - The execution times depend on the number of the new materials to be processed. 9.
STATUS 10.
REFERENCES - 11.
HARDWARE REQUIREMENTS - 12.
PROGRAMMING LANGUAGE -IAEA1420/01: 13.
SOFTWARE REQUIREMENTS - 14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - . 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE -IAEA1420/01: 17.
CATEGORIES - Keywords: ACCELERATOR DRIVEN SYSTEMS, CROSS SECTIONS, LIBRARIES, MONTE CARLO METHOD, NEUTRON, SN METHOD
Program-name Package-ID Status
ZZ-ADS-LIB/V1.0 IAEA1420/01 Tested
This test library can be used for a number of code systems in the analysis of Accelerator Driven Systems (ADS).
The library is restricted to those materials needed for benchmarking efforts linked to short and mid-term ADS experimental results and design concepts. The 30 materials selected and the upper energy limit of the evaluation of each of them is given in parentheses.
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FORMAT: ENDF-6
NUMBER OF GROUPS: continuous energy for ACE library
421 neutron groups for MATXS library
NUCLIDES: H-1 (150), O-16 (150), Al-27 (150), Ti-46 (20), Ti-47 (20), Ti-48 (20), Ti-49 (20), Ti-50 (20), Cr-50 (20), Cr-52 (20), Cr-53 (20), Cr-54 (20), Mn-55 (20), Fe-54 (200), Fe-56 (200), Fe-57 (200), Fe-58 (200), Ni-58 (20), Ni-60 (20), Ni-61 (150), Ni-62 (150), Ni-64 (150), Pb-204 (200), Pb-206 (200), Pb-207 (200), Pb-208 (200), Th-232 (20) , U-234 (20), U-235 (20), U-238 (30)
THERMAL SCATTERING
Thermal scattering Data for Hydrogen bound in water, 293.6 K, 323.6 K, 373.6 K, 423.6 K, 473.6 K, 523.6 K, 573.6 K, 623.6 K
TEMPERATURES:
for H-1: [293.6,323.6,373.6,423.6,473.6,523.6,573.6,623.6K]
for Actinides and O-16: [293.6, 400, 500, 600, 700, 800, 900, 1200K]
and for the rest of materials: [293.6, 400, 500, 600, 700, 800, 900K]
ORIGIN: JEFF3.1
NEUTRON WEIGHTING SPECTRUM:
standard PWR spectrum included in the GROUPR module of NJOY, modified in
such a way that follows the 1/E shape from 4.0 Ev to 9.811 KeV and from 10 to
20 MeV.
BACKGROUND SCATTERING:
sigma-0, between 5 and 10, depending on the nuclide in the range 1-10E10.
LEGENDRE ORDER:
P-6 for transport correction to P-5.
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IAEA1420/01: 13-FEB-2008 Tested at NEADB
[1] STANCULESCU A., TRKOV A.:
Application Libraries for ADS and Transmutation
15-17 December 2004, Vienna, Austria, INDC (NDS)-469.
[2] NEA/OECD: The JEFF-3.1 project: Complete content of the JEFF-3.1 evaluated
nuclear data library
June 2, 2005, NEA#06071 (on CDROM)
[3] MACFARLANE R.E., MUIR D.W.:
NJOY-99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B data
Los Alamos National Laboratory, PSR-480, 2000.
[4] BRIESMEISTER J.F.:
MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C
Los Alamos National Laboratory, LA-13709-M, 2000.
[5] RHOADES W.A., et al.:
DOORS 3.2, One-, Two-, Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System
RSICC, Oak Ridge National Laboratory, CCC-650, 1998.
[6] MCLANE V. (editor):
ENDF-6 Formats Manuals
IAEA-NDS-76 Rev. 6, April 2001.
[7] MACFARLANE R.E.:
TRANSX 2: A Code for Interfacing MATXS Cross Section Libraries to Nuclear Transport Codes
Los Alamos National Laboratory, LA-12312-MS, 1992.
[8] TRKOV A.:
Guidelines for Nuclear Data Verification and Validation
International Atomic Energy Agency, Vienna, INDC(SEC)-0107, August 2005.
[9] TRKOV A.:
Private communication on ACELST code
December 2002.
[10] CULLEN D.E.:
PREPRO 2004: 2004 ENDF/B Pre-processing codes (ENDF/B-VII Ready)
IAEA-NDS-39, Rev. 12, November 22, 2004.
IAEA1420/01:
- D. Lopez Aldama and A. Trkov:
ADS-Lib/V1.0, A test library for Accelerator Driven Systems
IAEA, INDC(NDS)-0474, August 2005
IAEA1420/01:
This version was tested at the NEA Databank on a PC with 3GHz INTEL Pentium 4.
IAEA1420/01:
This version was tested at the NEA Databank under WINDOWS XP Professional with the following compilers:
- g95 (g95);
- Compaq Visual Fortran Professional Edition 6.6 a (df);
- Lahey/Fujitsu Fortran 95 Compiler Release 5.50d (lf95).
IAEA1420/01:
Some small modifications have been introduced in the DOS .bat procedures to
increase the portability: some less important procedures have been eliminated since they use proprietary software.
D. Lopez Aldama and A. Trkov
Nuclear Data Section
International Atomic Energy Agency
Vienna, Austria
ENDF/ evaluated nuclear data files on which the library is based (JEFF3.1)
ACE/ processed ACE formatted files
MATXS/ MATXS and GENDF formatted files
Inputs/ Input files ADSNJI.INP, ADSNT.DAT, ADSSL.DAT
OUT/ output files from NJOY run
PEND/ PENDF files from NJOY run
Programs/ auxiliary programs and batch procedures
Work/ Working directory
Documents/ documentation
- Z. Data.
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