Using the source range monitor response to determine fuel relocation during the TMI-2 accident

Conference · Thu Jan 01 00:00:00 EST 1987 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:7098501

Baratta, A J; Wu, H Y; Hsiao, M Y; Bandini, B R; Tolman, E L

A number of researchers have analyzed the Three Mile Island Unit 2 (TMI-2) source range monitor (SRM) response during the TMI-2 accident. In each of these analyses, an intact core was assumed. Video and sonar inspections that took place during the defueling effort have shown that the core was extensively damaged. In this paper the authors report on an analysis of the TMI-2 SRM in which the times of fuel relocation were determined.

• Research Organization: Pennsylvania State Univ., University Park (USA)
• OSTI ID: 7098501
• Report Number(s): CONF-8711195-; TRN: 88-033595
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
THREE MILE ISLAND-2 REACTOR
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR MONITORING SYSTEMS
INSPECTION
RADIATION DETECTORS
REACTOR SAFETY
VOID FRACTION
ACCIDENTS
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THERMAL REACTORS
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220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
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