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AbstractAbstract
[en] Results from summation calculations by the CINDER-10 code 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. 37 figures, 12 tables
Original Title
FITPULS, in FORTRAN for CDC computers
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Source
Sep 1978; 114 p; Available from NTIS., MF A01
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Report
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