A nuclear cross section data handbook
Isotopic information, reaction data, data availability, heating numbers, and evaluation information are given for 129 neutron cross-section evaluations, which are the source of the default cross sections for the Monte Carlo code MCNP. Additionally, pie diagrams for each nuclide displaying the percent contribution of a given reaction to the total cross section are given at 14 MeV, 1 MeV, and thermal energy. Other information about the evaluations and their availability in continuous-energy, discrete-reaction, and multigroup forms is provided. The evaluations come from ENDF/B-V, ENDL85, and the Los Alamos Applied Nuclear Science Group T-2. Graphs of all neutron and photon production cross-section reactions for these nuclides have been categorized and plotted. 21 refs., 5 tabs.
- Research Organization:
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5354065
- Report Number(s):
- LA-11711-M; ON: DE90004990
- Country of Publication:
- United States
- Language:
- English
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ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
Related Subjects
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
PHOTONUCLEAR REACTIONS
COMPILED DATA
CROSS SECTIONS
MANUALS
MONTE CARLO METHOD
THEORETICAL DATA
BARYON REACTIONS
DATA
DOCUMENT TYPES
HADRON REACTIONS
INFORMATION
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
651000* - Nuclear Physics