Application of a Library of Processed ENDF/B-IV Fission-Product Aggregate Decay Data in the Calculation of Decay-Energy Spectra.

摘要

Results from summation calculations by the CINDER-10code and ENDF/B-IV decay,cross section,and yield data for fission pulses were incorporated into an ENDF/B-type format. The organization and content of this basic fine-group source-term library is described. In addition,two codes are described that provide pulse functions as fits to a user-specified multigrouping of the fine-group library. These can be readily used,essentially as Green's functions,to produce the spectra following any specific reactor power history. A particular set of fitted beta and gamma spectra having wide utility is described. Absorption effects are incorporated. 37figures, 12tables. (ERA citation 04:011736)