**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, ^{3}He, ^{4}He, ^{6}Li, ^{7}Li, ^{7}Be, ^{9}Be, ^{10}B, ^{11}B, ^{12}C, ^{14}N, ^{16}O, ^{19}F, ^{23}F,
^{Nat}Mg, ^{27}Al, ^{Nat}Si, ^{31}P, ^{32}S, ^{Nat}Cl, ^{Nat}Ar, ^{Nat}K, ^{Nat}Ca, ^{Nat}Ti, ^{51}V, ^{Nat}Cr, ^{55}Mn, ^{Nat}Fe, ^{59}Co, ^{Nat}Ni, ^{58}Ni, ^{Nat}Cu,
^{Nat}Ga, ^{Nat}Zr, ^{93}Nb, ^{Nat}Mo, ^{107}Ag, ^{109}Ag, ^{Nat}Cd, ^{Nat}Sn, ^{Nat}Ba, ^{Nat}Eu, ^{Nat}Gd, ^{165}Ho, ^{181}Ta, ^{Nat}W, ^{185}Re, ^{187}Re,
^{Nat}Pt, ^{197}Au, ^{Nat}Pb, ^{231}Th, ^{232}Th, ^{233}Th, ^{233}U, ^{234}U, ^{235}U, ^{236}U, ^{237}U, ^{238}U, ^{239}U, ^{240}U, ^{237}Np, ^{238}Pu, ^{239}Pu,
^{240}Pu, ^{241}Pu, ^{242}Pu, ^{243}Pu, ^{241}Am, ^{242m}Am, ^{243}Am, ^{242}Cm, ^{243}Cm, ^{244}Cm, ^{245}Cm, ^{246}Cm, ^{247}Cm, ^{248}Cm,
^{249}Bk, ^{249}Cf, ^{250}Cf, ^{251}Cf, ^{252}Cf, 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.

**KEYWORDS:** GAMMA-RAY CROSS SECTIONS; NEUTRON CROSS SECTIONS