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Title: MULTIGROUP CALCULATIONS OF EFFECTIVE NEUTRON FRACTION $beta$eff' PROMPT NEUTRON LIFETIME lp' AND RELATED KINETICS PARAMETERS FOR LARGE, FAST, PLUTONIUM-FUELED REACTORS

Technical Report ·
DOI:https://doi.org/10.2172/4785756· OSTI ID:4785756

Large, plutonium-fueled, fast reactors will have a different kinetic behavior than fast reactors fueled with U/sup 235/, due to the much smaller delayed-neutron fraction emitted in the fissioning of plutonium. The fissioning of Pu/sup 240/, Pu/sup 241/, Pu/sup 242/, and especially U/sup 238/, which emit mor e delayed neutrons per fission than Pu/sup 239/, introduces a considerable increase in BETA /sub eff/ over that for a hypothetical pure Pu/sup 239/ reactor. The cases considered are 800-, 1500-, and 2500-liter cores fueled with plutonium of different isotopic content, which lead to effective delayed-neutron fractions of approximately one-half the values of similar U/sup 235/-U/sup 238/-fueled fast reactors. The energy spectrum and the number of fissions weighted with their importance are recorded in order to reason physically on the obtained parameters. (auth)

Research Organization:
Argonne National Lab., Ill.
DOE Contract Number:
W-31-109-ENG-38
NSA Number:
NSA-16-029997
OSTI ID:
4785756
Report Number(s):
ANL-6423
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English