Analysis of sample and fuel pin irradiation experiments in Phenix for basic nuclear data validation

D'Angelo, A.; Cleri, F.; Marimbeau, P.; Salvatores, M.; Grouiller, J.P.

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Analysis of sample and fuel pin irradiation experiments in Phenix for basic nuclear data validation

D'Angelo, A.; Cleri, F.; Marimbeau, P.; Salvatores, M.; Grouiller, J.P.1990

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AbstractAbstract

[en] This paper presents comparisons between calculations and experimental data from fuel irradiation experiments performed in Phenix. Both the French CARNAVAL-IV system and the recently developed JEF-1 basic data file are used. The global consistency of the results is excellent and the compared values are, in general, very satisfactory. In some cases, indications for evaluated data modifications are obtained

Primary Subject

SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS (E3500)

Secondary Subject

NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION (F4000)

Record Type

Journal Article

Literature Type

Numerical Data

Journal

Nuclear Science and Engineering; ISSN 0029-5639;

; CODEN NSENA; v. 105(3); p. 244-255

Country of publication

United States

Descriptors (DEI)

CALCULATION METHODS, COMPARATIVE EVALUATIONS, EXPERIMENTAL DATA, FUEL PINS, IRRADIATION, NUCLEAR DATA COLLECTIONS, PHENIX REACTOR, VERIFICATION

Descriptors (DEC)

BREEDER REACTORS, DATA, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EVALUATION, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, INFORMATION, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, NUMERICAL DATA, PLUTONIUM REACTORS, POWER REACTORS, REACTOR COMPONENTS, REACTORS, SODIUM COOLED REACTORS

Reference NumberReference Number

23019630

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