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RSIC DATA LIBRARY DLC-120


1. NAME AND TITLE OF DATA LIBRARY

LENDL-V: Lawrence Livermore National Laboratory Evaluated Nuclear Data Library in ENDF-V Format.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM

None provided.

3. CONTRIBUTORS

IAEA Nuclear Data Section, Vienna, Austria.

Lawrence Livermore National Laboratory, Livermore, California.

4. HISTORICAL BACKGROUND AND INFORMATION

Earlier versions of the Livermore Evaluated Nuclear Data Library ENDL were translated into ENDF-IV format and packaged as DLC-34/LENDL. This version, in ENDF-V format, was assigned a new DLC number.

5. APPLICATION OF THE DATA

This library contains the Evaluated Nuclear Data Library (ENDL) of the Lawrence Livermore National Laboratory as of 1984. The library has been converted to the ENDF-V format by Lawrence Livermore National Laboratory and the IAEA Nuclear Data Section. The library contains evaluated neutron cross sections and differential data and neutron induced photon production data for 94 materials and includes a total of 231,348 records. All evaluations are complete, covering all relevant reactions for incident energies from 10-4 eV to 20 MeV. All cross sections are represented in tabulated linearly interpolable form; resonance parameters are not used.

6. SOURCE AND SCOPE OF DATA

The ENDL format is more general than the ENDF-V format in terms of the forms in which nuclear data can be represented in the ENDL format. As such it is not possible to accurately translate the entire ENDL library to the ENDF-V format. Evaluations which appear in the ENDL library in the ENDL format and not in the ENDF-V format include 2H and 9Be which use a double differential representation of the secondary energy-angle distribution in the ENDL format, which is not allowed in the ENDF-V format.

The materials included in the library are:

H, 3H, 3He, 4He, 6Li, 7Li, 7Be, 10B, 11B, 12C, 14N, 16O, 19F, 23Na, Mg, 27Al, Si, 32S, Cl, Ar, K, Ca, Ti, 51V, Cr, 55Mn, Fe, 59Co, Ni, 58Ni, Cu, Ga, 74As, 75As, 88Y, 89Y, Zr, 93Nb, Mo, 107Ag, 109Ag, Cd, Sn, 138Ba, Eu, Gd, 165Ho, Hf, 181Ta, W, 185Re, 187Re, Pt, 197Au, Pb, 209Bl, 231Th, 232Th, 233Th, 233U, 234U, 235U, 236U, 237U, 238U, 239U, 240U, 235Np, 236Np, 237Np, 238Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 243Pu, 241Am, 242mAm, 243Am, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm, 249Bk, 249Cf, 250Cf, 251Cf, 252Cf, Fiss. Prod.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.



8. DATA FORMAT AND COMPUTER

ENDF-V format; IBM 360.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCE

D. E. Cullen and P. K. McLaughlin, "The Lawrence Livermore National Laboratory Evaluated Nuclear Data Library in the ENDF-V Format," IAEA-NDS-11 Rev. 4 (May 1985).

11. CONTENTS OF LIBRARY

Included are the referenced document and one (1.2MB) DOS diskette which contains the Livermore Evaluated Nuclear Data Library in ENDF-V format.

12. DATE OF ABSTRACT

September 1986.

KEYWORDS: EVALUATED NEUTRON CROSS SECTIONS