Published 1980
| Version v1
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Ability of the TRAC-P1A computer program to predict blowdown, refill, and reflood phenomena during Semiscale Mod-1 experiments
Description
A computer analysis of a Semiscale Mod-1 Loss-of-Coolant Experiment (LOCE) was performed using the TRAC-P1A computer program. The main purpose of this analysis was to contribute data for the assessment of the ability of TRAC-P1A to predict blowdown, refill, and reflood phenomena during a postulated Loss-of-Coolant Accident (LOCA). A TRAC-P1A Semiscale Mod-1 system model was created and TRAC-P1A was used to obtain initial conditions for Semiscale Mod-1 LOCE S-04-6. After this initialization, TRAC-P1A was used to simulate the first 60 seconds of this experiment. The results of this simulation are presented and discussed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
11570393.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- CONF-800909--1
Conference
- Title
- Nuclear reactor safety heat transfer international seminar.
- Dates
- 1 - 5 Sep 1980.
- Place
- Dubrovnik, Yugoslavia.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11570393
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS