SAMARIUM TABLES

Technical Report · Tue Jan 31 23:00:00 EST 1961

OSTI ID:4049293

English, J C; Gorrell, T C

Tables ars presented that may be used to estimate the reactivity transients resulting from samarium poisoning in and thermal reactor that employs U/sup 235/ as the principal fissionable material. The Sm/sup 149/ concentration is given as a function of time in units of samarium absorptions per fis sion neutron. For enriched reactors, these units approximate closely the reactivity held in samarium. The thermal flux is expressed in units of megawatts from thermal fissions per kg of U/sup 235/. Table entries are spaced at flux increments of 0.2 in the range from 0.0 to 10.0. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Savannah River Lab., Aiken, S.C.; Du Pont de Nemours (E.I.) & Co. Savannah River Plant, Aiken, S.C.
• NSA Number: NSA-15-015212
• OSTI ID: 4049293
• Report Number(s): DP-557
• Country of Publication: United States
• Language: English

Related Subjects

ABSORPTION
DENSITY
ENRICHMENT
FISSION
NEUTRON FLUX
POISONING
POWER
REACTIVITY
REACTOR TECHNOLOGY
REACTORS
SAMARIUM
SAMARIUM 149
THERMAL NEUTRONS
TRANSIENTS
URANIUM 235