Computer Programs
DLC-0178 ZZ-SNLRML.
last modified: 23-MAY-1996 | catalog | categories | new | search |

DLC-0178 ZZ-SNLRML.

ZZ SNLRML, Dosimetry Cross-Section Recommendations

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1. NAME

ZZ-SNLRML.

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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name Package id Status Status date
ZZ-SNLRML DLC-0178/01 Tested 23-MAY-1996

Machines used:

Package ID Orig. computer Test computer
DLC-0178/01 Many Computers UNIX W.S.
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3. DESCRIPTION

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

 

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.

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6. TYPICAL RUNNING TIME
DLC-0178/01
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.
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8. RELATED OR 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.

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9. STATUS
Package ID Status date Status
DLC-0178/01 23-MAY-1996 Tested at NEADB
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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)

DLC-0178/01, included references:
- P.J. Griffin et al. :
  SNLRML Recommended Dosimetry Cross Section Compendium
  SAND92-0094 (November 1993)
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11. HARDWARE REQUIREMENTS
DLC-0178/01
The filesize of the SNLRML library file (ASCII) is 854  KByte.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
DLC-0178/01
The library SLNRML was tested by running the test case  of package SNL-SAND-II on a Sun Solaris platform under SunOS 5.3
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center

                Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA

 

Developed by:   Sandia National Laboratories

                Albuquerque, New Mexico, USA

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16. MATERIAL AVAILABLE
DLC-0178/01
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
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17. CATEGORIES
  • Z. Data

Keywords: ENDF/B, covariance matrices, dosimeters, evaluated data, neutron cross sections, nuclear damage.