Published November 1985
| Version v1
Report
Behaviour of fuel cladding under accident conditions
Description
The behaviour of the fuel cladding during accidental transients is a key phenomenon which determines whether an actual or a design basis accident will or will not lead to activity release to the coolant or to the environment; it determines also the extent of core damage which can possibly penalize further power plant operation. In off-normal and accidental situations, a strong chemical interaction may arise between Zircaloy and coolant. This results essentially from the chemical affinity of Zircaloy for oxygen, together with the thermodynamic conditions of the interaction. It is the objective of the present chapter to review this type of interaction, on the basis of some recent publications
Additional details
Publishing Information
- Imprint Title
- Fuel cladding interaction with water coolant in power reactors
- Imprint Pagination
- 225 p.
- Journal Page Range
- p. 189-209.
- Report number
- IAEA-TECDOC--356
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 17022887
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CORROSION; CRYSTAL-PHASE TRANSFORMATIONS; DESIGN BASIS ACCIDENTS; FUEL CANS; FUEL RODS; FUEL-CLADDING INTERACTIONS; FUEL-COOLANT INTERACTIONS; LOSS OF COOLANT; MECHANICAL PROPERTIES; PLANNING; RESEARCH PROGRAMS; REVIEWS; SPECIFICATIONS; STRESS CORROSION; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; DOCUMENT TYPES; FUEL ELEMENTS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 7 refs, 2 figs.