Determination of the coolant and core status during the TMI-2 accident from the ex-core detector responses

Thesis/Dissertation · Wed Jan 01 04:00:00 EST 1986

OSTI ID:6978913

Wu, H Y

This work investigated the ex-core detector response in a pressurized water reactor (PWR) during a small-break loss of coolant accident (LOCA), such as occurred at the Three Mile Island unit 2 (TMI-2) Nuclear Generating Station. The ex-core detector responses during several small-break LOCA experiments and the TMI-2 accident were analyzed. From this analysis, the progression of the core damage during the RMI-2 accident was determined. This analysis represents the first complete study of the source range monitor response and includes a determination of the coolant status, control rod melting, and fuel relocation during the TMI-2 accident. The study provides the first complete interpretation of the anomalous behavior of the SRM during the accident. The sensitivity study shows that the ex-core detector response depends on the region where voiding occurs. Voiding or a water level decrease in the downcomer region has a major effect on neutron leakage, and voiding or a water level decrease in the core region has the effect on the neutron multiplication and source strength in the core. An analysis of the source range monitor (SRM) response during TM-2 accident indicates that the response of the ex-core detector contains information on the coolant and core status during a small-break LOCA.

• Research Organization: Pennsylvania State Univ., University Park (USA)
• OSTI ID: 6978913
• Country of Publication: United States
• Language: English

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ACCIDENTS
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WATER COOLED REACTORS
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