Hydrogen-burn survival: preliminary thermal model and test results
This report documents preliminary Hydrogen Burn Survival (HBS) Program experimental and analytical work conducted through February 1982. The effects of hydrogen deflagrations on safety-related equipment in nuclear power plant containment buildings are considered. Preliminary results from hydrogen deflagration experiments in the Sandia Variable Geometry Experimental System (VGES) are presented and analytical predictions for these tests are compared and discussed. Analytical estimates of component thermal responses to hydrogen deflagrations in the upper and lower compartments of an ice condenser, pressurized water reactor are also presented.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6977565
- Report Number(s):
- NUREG/CR-2730; SAND-82-1150; ON: DE83001091
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of equipment survivability in hydrogen burns. [PWR]
Equipment survivability in hydrogen burns. [PWR; BWR]
Hydrogen-Burn Survival Program. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5870277
Equipment survivability in hydrogen burns. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5953636
Hydrogen-Burn Survival Program. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6756651
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINMENT
CONTAINMENT BUILDINGS
DETONATIONS
ELEMENTS
FIRES
HYDROGEN
LOSS OF COOLANT
NONMETALS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TEMPERATURE GRADIENTS
TEST FACILITIES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTAINMENT
CONTAINMENT BUILDINGS
DETONATIONS
ELEMENTS
FIRES
HYDROGEN
LOSS OF COOLANT
NONMETALS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TEMPERATURE GRADIENTS
TEST FACILITIES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS