Published June 1976
| Version v1
Report
Review of selected efforts at the Oak Ridge National Laboratory on core melt-through
Description
A listing of factors that should be considered to assure post-accident containment integrity in LMFBR's, a preliminary evaluation of penetration of concrete by a molten fuel mass following a core melt of an LWR, and an preliminary experimental survey of the ability of refractory materials to withstand molten UO2 are presented. Results are summarized in the synopsis of each part of the presentation
Additional details
Publishing Information
- Imprint Title
- Proceedings of Post-Accident Heat Removal (PAHR) information exchange
- Imprint Pagination
- p. 101-158.
- Report number
- SAND--75-0497
Conference
- Title
- Proceedings of post-accident heat removal information exchange.
- Dates
- 8 Oct 1974.
- Place
- Albuquerque, New Mexico, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8283830
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CORE CATCHERS; HEAT TRANSFER; LMFBR TYPE REACTORS; MELTDOWN; ORNL; PWR TYPE REACTORS; RESEARCH PROGRAMS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; US AEC; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS