CALCULATION OF DOPPLER COEFFICIENT AND OTHER SAFETY PARAMETERS FOR A LARGE FAST OXIDE REACTOR

Technical Report · Thu Mar 23 00:00:00 EST 1961

DOI:https://doi.org/10.2172/4834797· OSTI ID:4834797

Greebler, P; Hutchins, B A; Sueoka, J R

Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., Schenectady, N.Y.
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(04-3)-189
• NSA Number: NSA-15-030254
• OSTI ID: 4834797
• Report Number(s): GEAP-3646
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ABSORPTION
BERYLLIUM
CANNING
DISTRIBUTION
ECONOMICS
EXCURSIONS
EXPANSION
FAST NEUTRONS
FUEL CANS
FUEL ELEMENTS
FUELS
LEAKS
LIFETIME
LIQUID METAL COOLANT
NEUTRONS
OPERATION
OXIDES
PLUTONIUM 239
PLUTONIUM 240
QUANTITY RATIO
REACTIVITY
REACTOR SAFETY
REACTORS
REFLECTORS
SODIUM
SPECTRA
SPECTRAL SHIFT
STEELS
TEMPERATURE
URANIUM 238
VARIATIONS