1. NAME AND TITLE OF DATA LIBRARY

SNLRML: Recommended Dosimetry Cross Section Compendium.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is included with this package.

3. CONTRIBUTOR

Sandia National Laboratories, Albuquerque, New Mexico.

4. HISTORICAL BACKGROUND AND INFORMATION

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-161) libraries. The library format was selected for easy interface with spectrum determination codes such as SAND-II (CCC-112) and LSL-M2 (PSR-223) and the new PSR-345/SNL-SAND-II has been enhanced to interface with SNLRML.

5. APPLICATION OF THE DATA

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 sections in a 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-547) and MCNP (CCC-200), in order to compare calculated and measured activities for benchmark reactor experiments.

6. SOURCE AND SCOPE OF DATA

SNLRML contains 69 dosimetry cross sections (including 6 cover materials and 4 RML-specific sensors) and associated covariance matrices in the SAND-II 640 group energy structure. This version of the library (version 1.0) also includes 6 dosimetry cross sections that are not recommended but are included for comparison purposes. In addition, 6 common fissile contaminates in dosimetry-quality fission foils and 1 reaction that is under current study for neutron metrology applications are included.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

PSR-345/SNL-SAND-II, an enhanced version of SAND-II (CCC-112), is an iterative spectrum unfolding code and can interface with this package.

8. DATA FORMAT AND COMPUTER

ASCII card images; all computers (D00178/ALLCP/00).

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

In documentation:

P. J. Griffin, J. G. Kelly, T. F. Luera, J. VanDenburg, "SNL RML Recommended Dosimetry Cross Section Compendium," SAND92-0094 (November 1993).

Background information:

P. J. Griffin, J. G. Kelly, "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, J. G. Kelly, T. F. Luera, "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, J. G. Kelly, T. F. Luera, "Effect of ENDF/B-VI Cross Sections on Neutron Dosimetry," Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry held in Strassbourg, France on August 27-31, 1990, G. Tsotridis, R. Dierckx, P. D'Hondt, Eds., Kluer Academic Publishers, pp. 669-675 (1992).

11. CONTENTS OF LIBRARY

Included are the referenced document and a 3.5-inch DOS diskette which contains the data library and a README file.

12. DATE OF ABSTRACT

July 1994.

KEYWORDS: COVARIANCE MATRICES; DOSIMETRY CROSS SECTIONS; DAMAGE CROSS SECTIONS; REACTION CROSS SECTIONS; NEUTRON CROSS SECTIONS