Fission product release from high gap-inventory LWR fuel under LOCA conditions

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:5046367

Lorenz, R A; Collins, J L; Osborne, M F; Malinauskas, A P

Fission product release tests were performed with light water reactor (LWR) fuel rod segments containing large amounts of cesium and iodine in the pellet-to-cladding gap space in order to check the validity of the previously published Source Term Model for this type of fuel. The model describes the release of fission product cesium and iodine from LWR fuel rods for controlled loss-of-coolant accident (LOCA) transients in the temperature range 500 to 1200/sup 0/C. The basis for the model was test data obtained with simulated fuel rods and commercial fuel irradiated to high burnup but containing relatively small amounts of cesium and iodine in the pellet-to-cladding gap space.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5046367
• Report Number(s): CONF-800607-87(Draft)
• Country of Publication: United States
• Language: English

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