The Effect of Accident Conditions on the Molten Core Material Relocation into the Lower Head of a PWR Vessel with Application to TMI-2
Creators
- 1. University of California, Los Angeles (United States)
Description
The damage progression of the reactor core and the slumping mechanism of molten material to the lower head of the reactor vessel were examined through simulation of severe accident scenarios that lead to large-scale core damage. The calculations were carried out on a Three Mile Island Unit 2 configuration using the computer code SCDAP/RELAP5/MOD3.2.Different accident scenarios were simulated. The high-pressure injection and makeup flow rates were changed. The extreme case with no water being added during the accident was examined. Reflood by restart of coolant pump 2B was also studied. Finally, the size of the power-operated relief valve opening was also changed. The effects of these accident scenarios on the accident progression and the core damage process were studied.It is concluded that, according to code MOD3.2, the molten material slumped to the lower head of the reactor vessel when the junction of the top and side crusts failed after the molten pool had reached the periphery of the core. When the effective stress caused by pressure imbalance inside and outside of the crust became larger than the ultimate strength of the crust, the crust failed mechanically
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 132
- Journal Issue
- 2
- Journal Page Range
- p. 256-280
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37121223
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLANTS; DAMAGE; FLOW RATE; OPENINGS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR VESSELS; RELIEF VALVES; S CODES; SIMULATION; STRESSES; THREE MILE ISLAND-2 REACTOR; ULTIMATE STRENGTH; WATER
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; MECHANICAL PROPERTIES; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; VALVES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/