DLC-0178 ZZ-SNLRML.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-SNLRML.

3. DESCRIPTION OF PROGRAM OR FUNCTION


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  FORMAT: SAND-II

  NUMBER OF GROUPS: 640 group SAND-II group structure.

NUCLIDES: Cd, B, Au, S, Ni, Li, F, Na, Mg, Al, Si, P, Sc, Ti, Mn, Fe, Co, Cu, Zn, Zr, Nb, Mo, Rh, Ag, In, I, Th, U, Np, Pu, Am.,

ORIGIN: ENDF/B-VI, ENDF/B-V, IRDF-90, JENDL-3, JEF 2.2 and GLUCS data with special modifications from private communications.

  WEIGHTING SPECTRUM: flat

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SNLRML is a reactor dosimetry library that draws upon all available evaluated cross section libraries and selects the best evaluation for application to research reactor spectrum determinations. Many of the components of the SNLRML come from the ENDF/B-VI and IRDF-90 (DLC-0161) libraries. The library format was selected for easy interface with spectrum determination codes such as SAND-II (CCC-0112 and LSL-M2 (PSR-233) and the new PSR-0345/SNL/SAND-II  has  been  enhanced to interface with SNLRML.
The data is recommended for spectrum determination applications and  for the prediction of neutron activation of typical radiation sensor materials. The library has been tested for consistency of the cross  section in wide variety of neutron environments. The results and cautions from this testing have been documented. The data has been interfaced with radiation transport codes, such as TWODANT-SYS (CCC-0547) and MCNP (CCC-0200), in order to compare calculated and measured activities for benchmark reactor experiments.

4. METHOD OF SOLUTION:

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

6. TYPICAL RUNNING TIME:

The library SNLRML was tested at the NEA-DB on a Sun Solaris platform under SunOS 5.3, as input to the program SNL-SAND-II. A few seconds of elapsed time are required to run the SAND-II test case.

7. UNUSUAL FEATURES OF THE PROGRAM:

8. RELATED AND AUXILIARY PROGRAMS

PSR-0345/SNL-SAND-II, an enhanced version of SAND-II (CCC-0112), is an iterative spectrum unfolding code and can interface with this package.

10. REFERENCES

- P.J. Griffin et al.:
  Status of Neutron Dosimetry Cross Sections,
  Reactor Dosimetry ASTM STP 1228. Harry Farrar IV, E. Parvin
  Lippincott, John, G. Williams, and David W. Vehar,
  Eds., American Society for Testing and Materials, Philadelphia
  (1994)
- P.J. Griffin et al.:
  Effect of New Cross Section Evaluations on Spectrum
  Determinations, IEEE Transactions on Nuclear Science, Vol. 39,
  no.6, pp 2078-2085 (December 1992)
- P.J. Griffin et al.:
  Effect of ENDF/B-VI Cross Sections on Neutron Dosimetry,
  Proceedings of the Seventh ASTM-Euratom Symposium on Reactor
  Dosimetry held in Strasbourg, France on August 27-31, 1990,
  G. Tsotridis, R. Dierckx, P. D'Hondt, Eds., Kluer Academic
  Publishers, pp. 669-675 (1992)

- P.J. Griffin et al. :
  SNLRML Recommended Dosimetry Cross Section Compendium
  SAND92-0094 (November 1993)

11. MACHINE REQUIREMENTS:

The filesize of the SNLRML library file (ASCII) is 854  KByte.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:

The library SLNRML was tested by running the test case  of package SNL-SAND-II on a Sun Solaris platform under SunOS 5.3

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Sandia National Laboratories
                Albuquerque, New Mexico

File name	File description	Records
DLC0178_01.001	Information file of package ZZ-SNLRML	232
DLC0178_01.002	SNLRML (ASCII) library file	12109
DLC0178_01.003	DOS file-names	2