TMI-2 criticality analysis: parametric studies and overall results
Conference
·
OSTI ID:6763997
Three hypothetical disrupted core models were analyzed for the President's Commission on the Accident at Three Mile Island Unit 2. The purpose of this paper is to provide a summary of the results obtained from preliminary parametric studies and from the analyses of the disrupted core models. Hopefully, the implications from these results are useful in planning plant recovery operations. However, the scope of this study did not include a quantitative determination of the probable condition of the reactor core or, on the other end, the development of recommendations for specific actions to assure the criticality safety of the plant.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6763997
- Report Number(s):
- CONF-801107-32; TRN: 81-000147
- Resource Relation:
- Conference: ANS international conference, Washington, DC, USA, 17 Nov 1980
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
THREE MILE ISLAND-2 REACTOR
REACTOR CORE DISRUPTION
COMPARATIVE EVALUATIONS
CRITICALITY
MATHEMATICAL MODELS
REACTIVITY INSERTIONS
REACTOR SAFETY
ACCIDENTS
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled