TRAP-MELT users manual. [BWR; PWR]
In hypothetical meltdown accidents of light water reactors (LWR's), it is expected that radionulcides released from the melt will undergo chemical and physical changes and will deposit on various surfaces as they are transported through the primary system to the containment. It is of considerable interest to know what fraction of these released nuclides actually reaches the containment and is available for leakage to the environment. A radionuclide transport and deposition model was developed that is consistent in its sophistication with the emerging state of knowledge regarding radionuclide release from core melts and the thermal-hydraulic behavior of LWR primary systems during meltdown. TRAP-MELT is a modification and further development of the previously published TRAP-LOCA code developed by us for analysis of fission product transport and deposition in a terminated loss-of-coolant accident.
- Research Organization:
- Battelle Columbus Labs., OH (United States)
- OSTI ID:
- 6367082
- Report Number(s):
- NUREG/CR-0632; BMI-2017; TRN: 79-009054
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fission product transport analysis. Quarterly progress report, 1 October--31 December 1977. [TRAP-PWR/BWR code; TRAP-MELT code]
Aerosol release and transport program. Quarterly progress report, October-December 1982. [Oak Ridge National Laboratory; PWR; BWR; LMFBR]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
MELTDOWN
COMPUTER CODES
T CODES
FISSION PRODUCT RELEASE
RADIOACTIVITY TRANSPORT
PWR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
TWO-PHASE FLOW
ACCIDENTS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MECHANICS
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