Fission product data for thermal reactors. Final report. Part I. A data set for EPRI-CINDER using ENDF/B-IV

Technical Report · Wed Dec 01 04:00:00 EST 1976

DOI:https://doi.org/10.2172/7079316· OSTI ID:7079316

England, T. R.; Wilson, W. B.; Stamatelatos, M. G.

A four-group fission-product neutron absorption library, appropriate for use in thermal reactors, is described. All decay parameters are taken from ENDF/B-IV. The absorption cross sections are also processed from ENDF/B-IV files, first into a 154-group set and subsequently collapsed into the 4-group set described in this report. The decay and cross section data were used to form 84 linear chains in the CINDER code format. These chains contain all significant fission products having half-lives exceeding 4 hours--a total of 186 nuclides. A 12-chain set containing one pseudo-chain for use in spatial depletion calculations is described. This set accurately reproduces the aggregate absorption buildup of the 84 chains. This report describes the chains and processed data, results of comparison calculations for various fuels, and a comparison of calculated temporal fission-product absorption buildup with corresponding results from a long-term fuel irradiation and cooling integral experiment.

• Research Organization: Los Alamos Scientific Lab., N.Mex. (USA)
• OSTI ID: 7079316
• Report Number(s): EPRI-NP-356(Pt.1)
• Country of Publication: United States
• Language: English

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BARYON REACTIONS
BUILDUP
COMPUTER CALCULATIONS
CROSS SECTIONS
FISSION POISONS
FISSION PRODUCTS
HADRON REACTIONS
ISOTOPES
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR POISONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RADIOACTIVE MATERIALS
REACTOR MATERIALS
REACTORS
THERMAL REACTORS