TMI-2 accident: core heat-up analysis
Abstract
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.
- Authors:
- Publication Date:
- Research Org.:
- Electric Power Research Inst., Palo Alto, CA (USA). Nuclear Safety Analysis Center
- OSTI Identifier:
- 5235864
- Report Number(s):
- EPRI-NSAC-24
ON: DE82901453; TRN: 82-013425
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
Citation Formats
Ardron, K H, and Cain, D G. TMI-2 accident: core heat-up analysis. United States: N. p., 1981.
Web. doi:10.2172/5235864.
Ardron, K H, & Cain, D G. TMI-2 accident: core heat-up analysis. United States. https://doi.org/10.2172/5235864
Ardron, K H, and Cain, D G. 1981.
"TMI-2 accident: core heat-up analysis". United States. https://doi.org/10.2172/5235864. https://www.osti.gov/servlets/purl/5235864.
@article{osti_5235864,
title = {TMI-2 accident: core heat-up analysis},
author = {Ardron, K H and Cain, D G},
abstractNote = {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.},
doi = {10.2172/5235864},
url = {https://www.osti.gov/biblio/5235864},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1981},
month = {Thu Jan 01 00:00:00 EST 1981}
}
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