Fuel rod behavior in a nine-rod bundle tested in film boiling. [PWR]

Conference · Fri Jan 26 04:00:00 EST 1979

OSTI ID:6321640

Kerwin, D K; Hobbins, R R; Wehner, A S

Effects of film boiling on fuel rod behavior determined from posttest examination of the first nine-rod bundle test (Test PCM-5) conducted in the Power Burst Facility (PBF) are presented. The power-cooling-mismatch test was designed primarily to investigate the film boiling behavior of a fuel rod surrounded by other rods in film boiling, i.e., a center rod in an environment believed to be representative of that of a power reactor rod during a period of overpower or low flow operation. Secondary objectives were to investigate possible rod-to-rod film boiling propagation, and rod-to-rod failure propagation; and to provide baseline data on operation and response of bundles for future PBF bundle tests.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-06-1570
• OSTI ID: 6321640
• Report Number(s): CONF-790602-2
• Country of Publication: United States
• Language: English

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ACCIDENTS
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FUEL ELEMENT CLUSTERS
FUEL ELEMENT FAILURE
PBF REACTOR
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
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WATER MODERATED REACTORS