EXPERIMENTAL IRRADIATION STUDIES ON UO$sub 2$-CONTAINING FUEL ELEMENTS FOR THE NUCLEAR MERCHANT SHIP REACTOR PROGRAM

Technical Report · Wed Nov 11 04:00:00 EST 1959

OSTI ID:4173524

Lamale, G E; Smith, J C; Hare, A W; Dickerson, R F

Two series of capsules containing UO/sub 2/ clad with stainless steel were irradiated in ETR for the purpose of studying the properties after a moderate burnup in an efficiently cooled capsule in one series and a moderate burnup in a capsule designed to simulate the condition of overpower in the other series. Specimens in the flrst series of three capsules had an enrichment of 4% and were irradiated to a burnup of 0.1% U. The UO/sub 2/ did not show any significant effects that could be definitely attributed to radiation. Specimens in the second series of three capsules had an enrichment of 3% and were irradiated to a burnup of 0.05% U. Low-conductivity materials of low thermal neutron absorption cross section were used to surround the specimens and thermally insulate the fissioning UO/sub 2/. The UO/sub 2/ showed considerable change as a result of irradiation, chiefly in the formation of columnar grains and central voids in all three capsules. A sample of fission gas was taken from one of the capsules and its analysis for Xe/sup 133/ indicates that only approximately 5 x 10/sup -3/% was released from the UO/sub 2/. (auth)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-14-022109
• OSTI ID: 4173524
• Report Number(s): BMI-BW-651 & Add.
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ABSORPTION
BURNUP
COOLING
CROSS SECTIONS
DEFECTS
ENRICHMENT
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
GASES
IRRADIATION
METALS, CERAMICS, AND OTHER MATERIALS
PARTICLES
PROPULSION
RADIATION EFFECTS
REACTORS
SHIPS
STAINLESS STEELS
THERMAL CONDUCTIVITY
THERMAL INSULATION
THERMAL NEUTRONS
URANIUM DIOXIDE
VOIDS
XENON 133