Published 1979
| Version v1
Book
Models of core melt behaviour after a postulated reactor vessel melt-through
Description
In the unlikely event of reactor core debris melting through the reactor vessel after a postulated core meltdown it will contact the underlying substrate material. The subsequent behavior of the core-melt depends on the fractions of oxide fuel and stainless steel in the melt. Models for the penetration of an immiscible phase into a lower melting point substrate are developed and illustrative calculations presented. Factors where a more detailed understanding would enable the range of models considered to be reduced are indicated. 13 refs
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- International meeting on fast reactor safety technology
- Journal Page Range
- p. 2150-2159.
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19 - 23 Aug 1979.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12618882
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; HEAT TRANSFER; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; MELTDOWN; STAINLESS STEELS
- Descriptors DEC
- ACCIDENTS; ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS