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Reactor-fuel-independent reactivity determinations

Journal Article · · Nucl. Sci. Eng.; (United States)
OSTI ID:7343722
Curves for the reciprocal asymptotic period versus positive reactivity for ENDF/B-IV delayed neutron data are presented for /sup 232/Th, /sup 233/U, /sup 235/U, /sup 238/U, /sup 239/Pu, /sup 240/Pu, and /sup 241/Pu nuclides. A procedure is described for reducing the dependence of reactivity interpretations, through period measurements, on the nuclidic composition of the fuel. The sensitivity of the results to incremental changes in the delayed neutron parameters is also presented. Reactivity, in dollar units, is sensitive to the relative yields of the delayed neutron groups.
Research Organization:
Brookhaven National Lab., Upton, NY
OSTI ID:
7343722
Journal Information:
Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 61:4; ISSN NSENA
Country of Publication:
United States
Language:
English