SODIUM REACTOR EXPERIMENT FUEL IRRADIATION EXPERIENCE

Technical Report · Tue Sep 15 04:00:00 EDT 1959

OSTI ID:4220369

Ballif, J L; Hayward, B R; Walter, J H; Woolsey, C C

Nondestructive examinations of the unalloyed uranium fuel in the Sodium Reactor Experiment (SRE) showed no increase in cladding diameter after 850 Mwd/ Ton calculated maximum burnup. Some clad aminations at maximum burnups of 65, 105, 390, and 850 Mwd/Ton showed progressive irradiation-induced dimensional changes. Data showed maximum changes in --2.6% for the highest burnup. Surface conditions indicated progressive roughening with increasing fuel material burnup level. All surface and dimensional characteristics appeared to be directly related to burnup. Some relationship was found between surface roughening and fuel element surface temperature. The SRE fuel element design appears to be performing well. Fuel element cladding examinations indicated no apparent change in ductility after exposure to surface temperatures of about 850 F, with subsequent cycling resulting from startup and shutdown of the reactor. (auth)

• Research Organization: Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-13-021184
• OSTI ID: 4220369
• Report Number(s): NAA-SR-3887
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CONFIGURATION
DENSITY
DUCTILITY
EXPANSION
FUEL CANS
FUEL ELEMENTS
FUELS
IRRADIATION
LIQUID METAL COOLANT
METALLURGY AND CERAMICS
PLANNING
RADIATION EFFECTS
REACTORS
SHUTDOWN
SODIUM
SRE
STARTUP
STRESSES
SURFACES
TEMPERATURE
TESTING
URANIUM
VOLUME