DLC-0037 ZZ-EPR/37F.

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

3. DESCRIPTION OF PROBLEM OR FUNCTION


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  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.

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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.

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).

- 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:

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

File name	File description	Records
DLC0037_01.001	INFORMATION,JCL	60
DLC0037_01.002	SOURCE RETRIEVAL PROGRAM	143
DLC0037_01.003	LIBRARY	108491
DLC0037_01.004	INPUT FOR RETRIEVAL PROGRAM	1
DLC0037_01.005	OUTPUT OF RETRIEVAL PROGRAM	442