Coupled thermal-hydraulic/aerosol transport analysis capability for severe accidents
- 1. Electric Power Research Inst., Palo Alto, CA (USA)
- 2. Science Applications International Co., Hermosa Beach, CA (USA)
- 3. Argonne National Lab., IL (USA)
- 4. Science Applications International Corp., Los Altos, CA (USA)
Description
Fission product transport and thermal-hydraulic phenomena, occurring during the in-vessel phase of postulated accident progression, affect each other directly and significantly. It is important to couple the calculation of these processes to obtain accurate estimates of the magnitude and the timing of the release, of initial and revolatilized fission products from the primary system of a PWR, or the vessel of a BWR. The Electric Power Research Institute research efforts to obtain a functional and sophisticated coupled thermal-hydraulic/aerosol transport analysis capability are described. These are based on coupling the codes CORMLT, PSAAC (Primary System Accident Analysis Code) and RAFT (Reactor Aerosol Formation and Transport), which have been under development since 1982. Summary descriptions of these codes are also provided. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-020086-9
- Imprint Title
- Source term evaluation for accident conditions
- Imprint Pagination
- 777 p.
- Series
- Proceedings series.
- Journal Page Range
- p. 687-704.
Conference
- Title
- International symposium on source term evaluation for accident conditions.
- Dates
- 28 Oct - 1 Nov 1985.
- Place
- Columbus, OH (USA).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 17062769
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CORIUM; COUPLING; FISSION PRODUCT RELEASE; FISSION PRODUCTS; HYDRAULICS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; SOURCE TERMS; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; COLLOIDS; COOLING SYSTEMS; DISPERSIONS; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; SOLS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 14 refs, 1 fig, 2 tabs.
- Secondary number(s)
- IAEA-SM--281/54.