Published 1993
| Version v1
Report
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Modeling of HDR oil and cable fire tests
Creators
- 1. Sandia National Labs., Albuquerque, NM (United States)
- 2. Notre Dame Univ., IN (United States). Dept. of Aerospace and Mechanical Engineering
Description
This paper summarizes the calculations performed at Sandia National Laboratories using the COMPBRN fire model for the Heiss Dampf Reaktor (HDR) tests E41.7 and E42.2. A Sandia modified version of COMPBRN III was used for the calculations. Test E41.7 was on oil pool fire, and test E42.2 was cable fire. Both tests were conducted inside a small room within the HDR containment. Calculations were also performed for test E41.7 with the Notre Dame Fire Model. Hot gas layer temperatures and other relevant results are presented. Comparison with experimental data is made, where possible. A brief discussion on the problems encountered in the application of fire models to nuclear power plant fire modeling is also included
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE94005431; NTIS; US Govt. Printing Office Dep.Files
25036995.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- SAND--93-0554C
Conference
- Title
- 12. biennial conference for the International Association for Structural Mechanics in Reactor Technology (SMIRT 12).
- Dates
- 16-26 Aug 1993.
- Place
- Stuttgart (Germany).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25036995
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; ELECTRIC CABLES; FIRES; HDR REACTOR; OILS; REACTOR SAFETY; TESTING
- Descriptors DEC
- BWR TYPE REACTORS; CABLES; COMPUTER CODES; CONDUCTOR DEVICES; ELECTRICAL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; ORGANIC COMPOUNDS; OTHER ORGANIC COMPOUNDS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-94AL85000
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- CONF-930803--31.