TMI (Three Mile Island)-2 defueling conditions and summary of research findings
Conference
·
OSTI ID:6846185
The Three Mile Island Unit 2 accident was severe, with extensive melting of fuel, release of fission products, and relocation of a large quantity of molten fuel material onto the reactor vessel lower head. This molten material challenged the integrity of the reactor vessel, which remained intact. The post-accident condition of the plant presented an extremely difficult and complex plant recovery. Core defueling necessitated the development and use of tools and the application of methods not used previously in the nuclear industry. During the past 9 years, the TMI-2 accident has been a unique, invaluable source of information for improving and expanding the base of knowledge on severe accidents in power reactors. This paper presents the plant's post-accident condition, summarizes the primary results of research on progression of core damage and fission product behavior during the accident, and discusses the approach to defueling the reactor.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6846185
- Report Number(s):
- EGG-M-88069; CONF-880309-6; ON: DE88015103
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
DAMAGE
ENRICHED URANIUM REACTORS
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PWR TYPE REACTORS
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WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
DAMAGE
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
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REPAIR
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS