Published June 1980
| Version v1
Report
Three Mile Island system thermal-hydraulic analysis using TRAC
Description
The Three Mile Island (TMI) nuclear plant was modeled using the Transient Reactor Analysis Code (TRAC) and a preliminary calculation, which simulated the initial part of the accident that occurred on March 28, 1979, was performed. The purpose of this calculation was to provide a better understanding of the system thermal-hydraulic response during the first 3 h of the accident and to evaluate how well TRAC results compared to the overall accident scenario and measured system parameters. The calculated system pressure, loop temperatures, and pressurizer level are all in good agreement with measured data
Additional details
Publishing Information
- Imprint Title
- Thermal reactor safety
- Journal Page Range
- p. 579-581.
- Report number
- CONF-800403--(Vol.1)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11570343
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; REACTOR ACCIDENTS; REACTOR SAFETY; THREE MILE ISLAND-2 REACTOR
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS