1. NAME AND TITLE OF DATA LIBRARY

LENDL: Livermore Evaluated Neutron and Secondary Gamma-Ray Production Cross-Section Library in ENDF/B-IV Format.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAM

None provided.

3. CONTRIBUTOR

Lawrence Livermore Laboratory, Livermore, California.

4. HISTORICAL BACKGROUND AND INFORMATION

The package was updated with the addition of he 1978 version of the Livermore Evaluated Nuclear Data Library in ENDF/B-IV.

5. APPLICATION OF THE DATA

The system must supply reliable up-to-date data, select specific types of data on request, provide output in a variety of forms, and function rapidly and efficiently.

The evaluated nuclear data is used for neutron transport and related calculations. The data are grouped into major cross-section and parameter categories: (1) total elastic, capture, fission, and total inelastic, (2) total inelastic, discrete inelastic levels, and/or continuum, (3) reactions between neutrons and multiple particles in which at least one neutron is omitted, (4) reactions between neutrons and particles in which no neutrons are emitted.

6. SOURCE AND SCOPE OF DATA

Neutron, secondary gamma-ray production, and gamma-ray interaction cross sections are provided for most elements in the range from Z=0 to 98. LENDL has a lower energy limit of 1.0E-4eV versus 1.0E-5 for ENDF/B; secondary angular distributions for isotropic processes are not explicitly included.

Plots which contain sufficient cross-section structure and which present cross sections individually over compatible energy ranges were expanded. The cross sections which are at least 0.1% of the total cross sections were plotted. The capture cross section over some energy ranges for light isotopes was eliminated, but the resulting plots were clarified.

The materials included in the library are:

Neutron, Hydrogen, Deuteron, Triton, ³He, ⁴He, ⁶Li, ⁷Li, ⁷Be, ⁹Be, ¹⁰B, ¹¹B, ¹²C, ¹⁴N, ¹⁶O, ¹⁹F, ²³F, ^NatMg, ²⁷Al, ^NatSi, ³¹P, ³²S, ^NatCl, ^NatAr, ^NatK, ^NatCa, ^NatTi, ⁵¹V, ^NatCr, ⁵⁵Mn, ^NatFe, ⁵⁹Co, ^NatNi, ⁵⁸Ni, ^NatCu, ^NatGa, ^NatZr, ⁹³Nb, ^NatMo, ¹⁰⁷Ag, ¹⁰⁹Ag, ^NatCd, ^NatSn, ^NatBa, ^NatEu, ^NatGd, ¹⁶⁵Ho, ¹⁸¹Ta, ^NatW, ¹⁸⁵Re, ¹⁸⁷Re, ^NatPt, ¹⁹⁷Au, ^NatPb, ²³¹Th, ²³²Th, ²³³Th, ²³³U, ²³⁴U, ²³⁵U, ²³⁶U, ²³⁷U, ²³⁸U, ²³⁹U, ²⁴⁰U, ²³⁷Np, ²³⁸Pu, ²³⁹Pu, ²⁴⁰Pu, ²⁴¹Pu, ²⁴²Pu, ²⁴³Pu, ²⁴¹Am, ^242mAm, ²⁴³Am, ²⁴²Cm, ²⁴³Cm, ²⁴⁴Cm, ²⁴⁵Cm, ²⁴⁶Cm, ²⁴⁷Cm, ²⁴⁸Cm, ²⁴⁹Bk, ²⁴⁹Cf, ²⁵⁰Cf, ²⁵¹Cf, ²⁵²Cf, Crude fission product.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

ENDF/B-IV format; IBM 360. (D00034/I0360/01, /02)

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

R. W. Roussin, Informal Notes (December 1979).

R. J. Howerton, D. C. Cullen, M. H. MacGregor, S. T. Perkins, and E. F. Plechaty, "The LLL Evaluated-Nuclear-Data-Library (ENDL): Graphs of Cross Sections from the Library," UCRL-50400, Vol. 15 (October 1978).

11. CONTENTS OF LIBRARY

Included are the referenced documents and two (1.44 MB) diskettes in self-extracting compressed DOS files, which contain the Livermore Evaluated Nuclear Data Library in ENDF/B-IV format. Version /02 is available on three (1.44 MB) diskettes in self-extracting compressed DOS files or one DC6150 tape cartridge in TAR format.