DLC-0037: ZZ EPR/37F, 100 Neutron-Group, 21 Gamma-Group Coupled Cross-Section for Experimental Power Reactor (EPR) Fusion System

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DLC-0037 ZZ-EPR/37F. (Abstract last modified 01-DEC-1979)

ZZ EPR/37F, 100 Neutron-Group, 21 Gamma-Group Coupled Cross-Section for Experimental Power Reactor (EPR) Fusion System

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION OF PROGRAM - ZZ-EPR/37F.

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

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.

Program-name Package-ID Status ZZ-EPR/37F DLC-0037/01 Tested ZZ-EPR/37E DLC-0037/02 Obsolete

Machines used: Package-ID Orig.Computer Test Computer DLC-0037/01 IBM 370 series IBM 370 series

3. DESCRIPTION OF PROBLEM OR FUNCTION -
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
  FORMAT: ANISN
  NUMBER OF GROUPS: 100 neutron, 21 gamma ray
NUCLIDES: Ni, Cr, Fe, Mn, Co, Cu, He, C, O, Al, Pb, Li, B, H, Be, V, Nb, Ti, F, Si, Mg, K, Na, N, Mo, Zr, U, P, S, Sn, Cl, Ca, Np, Pu, Au, W, Ta, Th, D.
  ORIGIN: ENDF/B-IV
WEIGHTING SPECTRUM: 1/E weighted for neutron energies exceeding 0.345 eV, below this energy a Maxwellian distribution peaked at 800K is used. The photon interaction cross sections are flat weighted.
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
This multigroup library is intended for use in neutronics calculations for the conceptual designs of the Experimental Power Reactor (EPR) and other fusion reactor models.
The data is in ANISN format, and has a coupled 100 neutron, 21 gamma ray energy group structure. The neutron groups include the 99 GAM- II epithermal and fast groups, together with a thermal group. All data sets exist for a P8 order of Legendre expansion, except those for tungsten which are P3.
Neutron and photon production cross sections are 1/E weighted for neutron energies exceeding 0.345 eV; below this energy a Maxwellian distribution peaked at 800 K is used. The photon interaction cross sections are flat weighted.

4. METHOD OF SOLUTION - Selected modules of the AMPX system were used to generate the data sets from the latest ENDF/B data.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM -

6. TYPICAL RUNNING TIME -

7. UNUSUAL FEATURES OF THE PROGRAM -

8. RELATED AND AUXILIARY PROGRAMS - The coupled 100 energy group neutron and 21 energy group gamma-ray ANISN-formatted cross section library has been modified by the addition of Si, Mg, K, Na, N, Mo, Zr, U-235, U-238, P-31, S-32, Sn, Cl, Ca, W-182, W-183, W-184, W-186, W (natural), and Nb (ENDF/B-IV) cross sections, by the addition of data sets containing B-10(n,t)2alpha, B-10(n,alpha), B-11(n,t), B-11(n,alpha), Li-6(n,t), Li-6(n,t) "hot", and Li-7 (n,n't) cross sections, and by the addition of a data set of kerma factors. The 100 energy group neutron master cross section library was modified by the addition of Nb, Zr, Ka, K, Mo, Si, Mg, N, Cl, Ca, P-31, S-32, Sn, U-235, U-238, W-182, W-183, W-184, and W-186 data sets.

9. STATUS
DLC-0037/01: 01-MAR-1980 Tested at NEADB
DLC-0037/02: 01-DEC-1979 Obsolete

10. REFERENCES  -
- D.M. Plaster, R.T. Santoro, W.E. Ford III:
  Coupled 100-Group Neutron and 21-Group Gamma-Ray Cross Sections
  for EPR Calculations.
  ORNL-TM-4872 (April 1975).
DLC-0037/01:
- W.E. Ford and B.R. Diggs to R.T. Santoro:
  Modification No. 18 to the ANISN-formatted EPR Cross-Section
  Library, Internal Correspondence (May 1978)
- W.E. Ford and B.R. Diggs to R.T. Santoro:
  Modification No. 17 to EPR Cross-Section Libraries,
  Internal Correspondence (October 1977)
- W.E. Ford and B.R. Diggs to R.T. Santoro:
  Modification No. 16 to EPR 100-218 Cross-Section Library,
  Internal Correspondence (February 17th., 1977)
- W.E. Ford, R.T. Santoro, R. W. Roussin, D. M. Plaster:
  Modification Number One to the Coupled 100n-218 Cross-Section
  Library for EPR Calculations, ORNL/TM-5249 (March 1976) (up-
  dated 11-7-78)
- L.R. Williams:
  Instructions for LIBGEN, a Code to convert from Card Image to
  Binary ANISN Format, Informal Notes (1972)

11. MACHINE REQUIREMENTS -

12. PROGRAMMING LANGUAGE(S) USED -
DLC-0037/01: FORTRAN-IV

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED -

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS -

15. NAME AND ESTABLISHMENT OF AUTHOR -
          Neutron Physics Division
          Oak Ridge National Laboratory
          Oak Ridge
          Tennessee
          USA

16. MATERIAL AVAILABLE -
DLC-0037/01:
DLC0037_01.001    INFORMATION,JCL                                    60 records
DLC0037_01.002    SOURCE RETRIEVAL PROGRAM                          143 records
DLC0037_01.003    LIBRARY                                        108491 records
DLC0037_01.004    INPUT FOR RETRIEVAL PROGRAM                         1 records
DLC0037_01.005    OUTPUT OF RETRIEVAL PROGRAM                       442 records

17. CATEGORIES  -

- X.  Magnetic Fusion Research
- Z.  Data.

Keywords: COUPLED NEUTRON GAMMA CROSS SECTIONS, CROSS SECTIONS, DATA, FUSION REACTORS, MULTIGROUP

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