TMI-2 accident: core heat-up analysis

Technical Report · Thu Jan 01 00:00:00 EST 1981

DOI:https://doi.org/10.2172/5235864· OSTI ID:5235864

Ardron, K H; Cain, D G

This report summarizes NSAC study of reactor core thermal conditions during the accident at Three Mile Island, Unit 2. The study focuses primarily on the time period from core uncovery (approximately 113 minutes after turbine trip) through the initiation of sustained high pressure injection (after 202 minutes). The transient analysis is based upon established sequences of events; plant data; post-accident measurements; interpretation or indirect use of instrument responses to accident conditions.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA). Nuclear Safety Analysis Center
• OSTI ID: 5235864
• Report Number(s): EPRI-NSAC-24; ON: DE82901453; TRN: 82-013425
• 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
ACTIVITY LEVELS
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
REACTOR CORES
ACCIDENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MECHANICS
POWER REACTORS
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REACTOR COMPONENTS
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THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled