Modeling of HDR oil and cable fire tests
Conference
·
OSTI ID:10116010
- Sandia National Labs., Albuquerque, NM (United States)
- Notre Dame Univ., IN (United States). Dept. of Aerospace and Mechanical Engineering
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.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10116010
- Report Number(s):
- SAND--93-0554C; CONF-930803--31; ON: DE94005431; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fire modeling of the Heiss Dampf Reaktor containment
Numerical Simulation of a Compartment Fire in a Nuclear Power Plant Containment Building
HECTR (Hydrogen Event: Containment Transient Response) assessment of the HDR (Heiss Dampf Reaktor) experiments
Technical Report
·
Fri Sep 01 00:00:00 EDT 1995
·
OSTI ID:113685
Numerical Simulation of a Compartment Fire in a Nuclear Power Plant Containment Building
Conference
·
Mon Jul 01 00:00:00 EDT 2002
·
OSTI ID:21070081
HECTR (Hydrogen Event: Containment Transient Response) assessment of the HDR (Heiss Dampf Reaktor) experiments
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5960733
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
ELECTRIC CABLES
FIRES
HDR REACTOR
MATHEMATICS AND COMPUTERS
OILS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REACTOR SAFETY
TESTING
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
C CODES
COMPUTER CALCULATIONS
COMPUTERIZED SIMULATION
ELECTRIC CABLES
FIRES
HDR REACTOR
MATHEMATICS AND COMPUTERS
OILS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
REACTOR SAFETY
TESTING