THE EXAMINATION AND EVALUATION OF IRRADIATED THORIUM-11 w/o URANIUM SPECIMENS

Technical Report · Thu Apr 16 00:00:00 EST 1959

DOI:https://doi.org/10.2172/4253908· OSTI ID:4253908

Gates, J. E.; Lamale, G. E.; Dickerson, R. F.

Twelve irradiated specimens of thorium -11 wt.% U were examined. The specimens were fabricated by induction melting and casting in graphite and cold swaging to about 42% reduction in area. The irradiations were conducted in the MTR in capsules equipped with thermocouples. Six specimcns were irradiated to burnups ranging from 0.5 to 0.6 total at.% at average central corc temperatures ranging from 1070 to 1250 F. Three spccimens exbibited sevcre swelling or decrepitation and three appeared to be in relatively good condition. The density of these specimens decreased from 4.9 to 9.9%. The remaining six specimens were irradiated to burnups ranging from 0.9 to 1.5 total at.% at average central core temperatures ranging from 970 to 1100 F. These specimens were in relatively good condition, except for three that had swollen sevcrely at one end. Density decreases ranging from 2.4 to 3.8% were determined for these specimens. Swelling of all specimens appeared to be a linear function of burnup to the highest level studied (l.5 total at.%) and at temperatures below about 1100 F. Swelling increased significantly above 1100 F, even at burnups as low as 0.2 at.%. Fission-gas losses averaged about 0.5% for sound specimens after burnups of 1.2 to 3.3 total at.% at around l100 F. These losses were due to diffusion and recoil; cracked specimens exhibited higher losses, Metallographic examination of the specimens indicated that neither thc matrix material nor the fuel material was seriously affected by the irradiation. No evidence of corrosion by the NaK heat-transfer medium was present. (auth)

• Research Organization: Battelle Memorial Inst., Columbus, OH (United States)
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-13-013516
• OSTI ID: 4253908
• Report Number(s): BMI-1334
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United States
• Language: English

Related Subjects

METALLURGY AND CERAMICS
BURNUP
CASTING
COLD WORKING
CORROSION
CRACKS
DENSITY
DIFFUSION
EXPANSION
FABRICATION
FISSION PRODUCTS
FUEL CANS
GASES
GRAPHITE
HEAT TRANSFER
HIGH TEMPERATURE
INDUCTION
INTERMETALLIC COMPOUNDS
IRRADIATION
MATERIALS TESTING
MELTING
METALLOGRAPHY
MTR
POTASSIUM ALLOYS
RADIATION EFFECTS
REACTORS
RESEARCH REACTORS
SAMPLING
SODIUM ALLOYS
TEMPERATURE
THERMOCOUPLES
THORIUM ALLOYS
URANIUM ALLOYS