DLC-0168 ZZ-LA100.

ZZ-LA100.

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FORMAT: ENDF/B-VI (MCNP)

NUMBER OF GROUPS: --

NUCLIDES: 1H, 9Be, 12C, 16O, 27Al, 28Si, Fe, W, and 238U.

ORIGIN: ENDF/B-VI

WEIGHTING SPECTRUM: --

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ZZ-LA100 Evaluated Nuclear Data Library for Transport Calculations Involving Incident Neutrons and Protons of Energy Up to 100 MeV. This data base was developed for use in Monte Carlo or discrete ordinate transport codes, for example, the general Monte Carlo code MCNP. Various modules of the NJOY processing code system have been enhanced to permit processing of the ENDF/B-VI formatted evaluations into both continuous-energy and multi-group format. The transport data files for all 18 projectile-plus-target systems have been processed through NJOY, and coupled multi-particle, multi-group transport libraries for MCNP now exist. In addition, pointwise MCNP libraries to 100 MeV for incident neutrons have been prepared for the nine targets. The production version of the MCNP code is being modified to handle the new pointwise libraries. The production version of MCNP already supports the use of coupled multi-group libraries.

The library is based on nuclear theory/model calculations with parameterizations obtained by matching calculations with experimental data, mainly using the PSR-125/GNASH statistical/preequilibrium/fission theory code. The library includes neutron- and proton-induced reactions for H1, Be9, C12, O16, Al27, Si28, Fe, W, and U238 and specifies the production cross sections and energy-angle correlated spectra of emitted neutrons, protons, alpha-particles, photons, and other significant charged particles. See reference LA-11753-MS for details.

Depends on the problem.

• E.D. Arthur: The GNASH Preequilibrium-Statistical Model Code lectures presented during the Workshop on Applied Nuclear Theory and Nuclear Model Calculations for Nuclear Technology Applications, International Centre for Theoretical Physics, Triest, Italy, 15 February - 18 March 1988 (LA-UR 88-283).

• P.G. Young, E.D. Arthur, and M.B. Chadwick: Comprehensive Nuclear Model Calculations - Introduction to the Theory and Use of the GNASH Code  lectures presented during the Workshop on Computation and Analysis of Nuclear Data Relevant to Nuclear Energy and Safety, International Centre for Theoretical Physics, Triest, Italy, 10 February - 13 March 1992 (LA-UR 92-205).

• R.E. MacFarlane, D.W. Muir, and R.M. Boicourt: The NJOY Nuclear Data Processing System Los Alamos National Laboratory report LA-9303-M (1982) v. I and II, (1987) v. III, (1985) v. IV.

• R.E. MacFarlane: Introducing NJOY 89, presented at the OECD Seminar-Workshop on NJOY and THERMIS, Nuclear Energy Agency Data Bank, Saclay, France, June 20-21, 1989 (LA-UR-89-2057 (1989)).

• J.F. Briesmeister, Ed.,: MCNP - A General Monte Carlo Code for Neutron and Photon Transport Version 3A, Los Alamos National Laboratory manual LA-7396-M Rev. 2 (Sept. 1986).

• J.F. Briesmeister: MCNP3B Newsletter LANL Memo. X-6:JFB-88-292 (July 18, 1988).

Los Alamos National Laboratory
Los Alamos, NM, USA