Application of the TEMPEST computer code for simulating hydrogen distribution in model containment structures. [PWR; BWR]
Conference
·
OSTI ID:5845592
In this study several aspects of simulating hydrogen distribution in geometric configurations relevant to reactor containment structures were investigated using the TEMPEST computer code. Of particular interest was the performance of the TEMPEST turbulence model in a density-stratified environment. Computed results illustrated that the TEMPEST numerical procedures predicted the measured phenomena with good accuracy under a variety of conditions and that the turbulence model used is a viable approach in complex turbulent flow simulation.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5845592
- Report Number(s):
- PNL-SA-10781; CONF-830103-45; ON: DE83002725
- Resource Relation:
- Conference: 2. international topical meeting on nuclear reactor thermal hydraulics (ANS), Santa Barbara, CA, USA, 11 Jan 1983; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
Similar Records
TEMPEST code simulations of hydrogen distribution in reactor containment structures. Final report
Application of the TEMPEST computer code to canister-filling heat transfer problems
Pressurized thermal shock: TEMPEST computer code simulation of thermal mixing in the cold leg and downcomer of a pressurized water reactor. [Creare 61 and 64]
Technical Report
·
Fri Mar 01 00:00:00 EST 1985
·
OSTI ID:5845592
Application of the TEMPEST computer code to canister-filling heat transfer problems
Technical Report
·
Tue Mar 01 00:00:00 EST 1988
·
OSTI ID:5845592
Pressurized thermal shock: TEMPEST computer code simulation of thermal mixing in the cold leg and downcomer of a pressurized water reactor. [Creare 61 and 64]
Technical Report
·
Sun Apr 01 00:00:00 EST 1984
·
OSTI ID:5845592
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
LOSS OF COOLANT
CONTROLLED ATMOSPHERES
PWR TYPE REACTORS
COMPUTER CALCULATIONS
HYDROGEN
MIXING
REACTOR SAFETY
SPATIAL DISTRIBUTION
TIME DEPENDENCE
ACCIDENTS
ATMOSPHERES
CONTAINMENT
DISTRIBUTION
ELEMENTS
NONMETALS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
LOSS OF COOLANT
CONTROLLED ATMOSPHERES
PWR TYPE REACTORS
COMPUTER CALCULATIONS
HYDROGEN
MIXING
REACTOR SAFETY
SPATIAL DISTRIBUTION
TIME DEPENDENCE
ACCIDENTS
ATMOSPHERES
CONTAINMENT
DISTRIBUTION
ELEMENTS
NONMETALS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled