Improvements in modelling (by ESCADRE mod1.0) radiative heat losses through gas and aerosols generated by molten corium-concrete interactions
- 1. ENEA CR Casaccia, Rome (Italy). Dipt. Energia
- 2. CEA Cadarache, St. Paul-lez-Durance (France)
Description
Aerosols generated during the molten core-concrete interaction (MCCI) influence the reactor cavity thermal hydraulics: the cloud of aerosols, located inside the reactor cavity, restrains the upward-directed heat exchange consequently the cool-down of the high-temperature molten corium for a considerable period of time. IPSN is developing a computer code system for source predictions in severe accident scenarios. This code system is named ESCADRE. WECHSL/CALTHER is internal module dealing with MCCI (it is also a stand-alone code): it models the heat transfers involving the superior volume of the cavity. When modelling the upward-directed power distribution by WECHSL/CALTHER, a faster concrete basemat penetration takes place due to the low heat losses of the closed MCCI cavity enclosure. The model, here presented, is going to be validated with data from the AEROSTAT experiment. This experiment, planned at CEA Cadarache, will evaluate the influence of aerosols on the global power distribution in the reactor cavity. Radiative heat losses are important especially for cavity configurations such as those of new plant designs (equipped with a core-catcher) where the upward power losses are promoted by the corium spreading in a flat cavity
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1226-X
- Imprint Title
- ICONE-4: Proceedings. Volume 3: Safety and reliability
- Imprint Pagination
- 595 p.
- Journal Page Range
- p. 229-235.
Conference
- Title
- ASME/JSME international conference on nuclear engineering.
- Acronym
- ICONE 4
- Dates
- 10-13 Mar 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27062876
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AEROSOLS; CONCRETES; CONTAINMENT SYSTEMS; COOLING; CORIUM; E CODES; HEAT TRANSFER; HYDRAULICS; MITIGATION; POWER DISTRIBUTION; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; SOURCE TERMS; SYNTHESIS; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; COLLOIDS; COMPUTER CODES; CONTAINMENT; DATA; DISPERSIONS; DISTRIBUTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; INFORMATION; MATERIALS; NUMERICAL DATA; SOLS; SPATIAL DISTRIBUTION
Optional Information
- Secondary number(s)
- CONF-960306--.