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