Published 1985
| Version v1
Report
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Assessment of TRAC-BD1/MOD1 using FIST data
Description
This report is concerned with the assessment of the TRAC-BD1/MOD1 Code, developed at Idaho National Engineering Laboratory. The assessment was conducted using data from the FIST (Full Integral Simulation Test) facility, which is a BWR safety test facility which was built to investigate small break LOCA and operational transients in BWR's and to complement earlier large break LOCA test results from TLTA (Two-Loop Test Apparatus). 21 figs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86005273.Files
18019601.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- BNL-NUREG--37325
Conference
- Title
- 13. water reactor safety research information meeting.
- Dates
- 22-25 Oct 1985.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18019601
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; REACTOR SAFETY; RISK ASSESSMENT; TESTING
- Descriptors DEC
- ACCIDENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8510173--48.