Applications of HECTR to reactor containments. [PWR; BWR]
Conference
·
OSTI ID:6651954
This paper presents the results of calculations performed with HECTR, a computer program developed at Sandia National Laboratories to model nuclear plant containment responses to transients that include hydrogen burns. Calculations were performed for Grand Gulf, a Mark III boiling water reactor, and Sequoyah, a pressurized water reactor with ice condensers. The transients analyzed were for a stuck-open relief valve and a small break loss-of-coolant accident (LOCA). Failure of emergency core coolant injection was assumed for both transients, leading to the production of a significant amount of hydrogen. Both Grand Gulf and Sequoyah are equipped with deliberate hydrogen ignition systems which were designed to ignite hydrogen/air mixtures at low hydrogen concentrations; the intent is to subject the containment to lower peak pressures than would occur if larger concentrations accumulated and were accidently ignited. HECTR calculations were performed for both plants to determine the containment response to the transients including burns due to deliberate ignition.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Dikewood Corp., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6651954
- Report Number(s):
- SAND-82-1969C; CONF-821026-8; ON: DE83000315
- Country of Publication:
- United States
- Language:
- English
Similar Records
HECTR analysis of hydrogen burns in PWR large dry containments
Evaluation of HECTR predictions on hydrogen transport. [PWR; BWR]
Multiple hydrogen-air deflagrations in containment and the resulting thermal environments. [PWR; BWR]
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5358070
Evaluation of HECTR predictions on hydrogen transport. [PWR; BWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5931664
Multiple hydrogen-air deflagrations in containment and the resulting thermal environments. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:5114624
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT BUILDINGS
ECCS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
EXPLOSIONS
FAILURES
HYDROGEN
NONMETALS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT BUILDINGS
ECCS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
EXPLOSIONS
FAILURES
HYDROGEN
NONMETALS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS