Published 1995
| Version v1
Book
AGR fuel damage resulting from flask drops
Description
The paper begins with a description of an AGR fuel element and of the results obtained from buckling tests on irradiated pins. The results of the drop tests are then assessed. Finally, assessments are made for drops of irradiated fuel in the conditions of interest. (author)
Additional details
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (United Kingdom)
- ISBN
- 0 7277 2033 3
- Imprint Title
- Fuel management and handling. Proceedings
- Imprint Pagination
- 368 p.
- Journal Page Range
- p. 233-238.
Conference
- Title
- International conference on fuel management and handling.
- Dates
- 20-22 Mar 1995.
- Place
- Edinburgh (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 28050304
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; DEFORMATION; DUCTILITY; FUEL CANS; FUEL PINS; IMPACT SHOCK; IMPACT TESTS; MATERIALS HANDLING; RUPTURES; SPENT FUEL CASKS; SPENT FUEL ELEMENTS
- Descriptors DEC
- CASKS; CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; REACTOR COMPONENTS; REACTORS; TENSILE PROPERTIES; TESTING