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RSIC DATA LIBRARY DLC-039

1. NAME AND TITLE OF DATA LIBRARY

UKNDL: United Kingdom Evaluated Neutron Cross-Section Data Library.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is included in the package.

3. CONTRIBUTOR

United Kingdom Atomic Energy Agency, Winfrith, Dorchester, Dorset, England, through the OECD Nuclear Energy Agency Computer Programme Library, Ispra, Italy.

4. HISTORICAL BACKGROUND AND INFORMATION

The main tape NDL-1 of the UK Nuclear Data Library containing 64 complete data files of neutron cross-sections for 60 different materials was re-edited. The contents of this tape lists the materials and data file numbers together with some convenient derived integral parameters and the energy range spanned by each partial cross-section. A request put forward to the IAEA Vienna Panel on Neutron Nuclear Data Evaluation in September, 1971, caused the data files to be rearranged into mass-ascending order.

5. APPLICATION OF THE DATA

UKNDL summarizes the content of the revised main tape NDL-1 of the UKNDL. It quotes the energy range of cross-section tabulations together with a list of tabulated reactions. It refers to the data sources and comments on their origin and newness.

For the fission-product range, Z = 30 to 68, UKNDL gives a comparative table of integral characteristics computed from capture cross-sections in the evaluated data files presently available in the format of the UK Nuclear Data Library. Similar data relating to the ENDF/B3 data library are also included. The integral characteristics listed are: (1) Thermal average cross-sections, (2) Resonance integrals, including the 1/v component, (3) Fission spectrum averages.

6. SOURCE AND SCOPE OF DATA

Many of the files are completely new or they represent extensive revisions of older files. Some have been converted from the American ENDF/B data library by use of the conversion code MISSIONARY. The exact masses have been revised as well as many of the reaction Q-values.

The data files on the UKNDL Main Tape, NDL-1, are as follows:

H in H2O, D in D2O, T, 3He, 4He, 6Li, 7Li, 9Be, 10B, 11B, C, N, O, 19F, 23Na, 27Al, Si, Cl, K, Ca, Ti, V, Cr, Fe, Ni, Cu, 63Cu, 65Cu, Ga, Zr, 93Nb, Mo, 107Ag, 109Ag, Cd, 113Cd, 135Xe, 151Eu, 153Eu, Ta, W, 197Au, Pb, 232Th, 233Pa, 233U, 234U, 235U, 236U, 238U, 239U, 240U, 238Pu, 239U, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

BCD card images; IBM 370.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

A. L. Pope, "The Current Edition of the Main Tape NDL-1 of the UK Nuclear Data Library--March 1973," AEEW--M 1208 (December 1973).

A. L. Pope and J. S. Story, "Thermal Average, Resonance Integral and Fission-Spectrum Average Neutron Capture Cross-Sections of Nuclides with X = 30 to 68," AEEW-M 1234 (December 1973).

11. CONTENTS OF LIBRARY

Included are the referenced documents and 1 tape cartridge in TAR format which contains the cross section library materials.

12. DATE OF ABSTRACT

December 1984.

KEYWORDS: EVALUATED NEUTRON CROSS SECTIONS; NEUTRON CROSS SECTIONS