Published 1987
| Version v1
Book
Laboratory simulation of rod-to-rod mechanical interactions during postulated loss-of-coolant accidents in a PWR involving cladding oxidation
Creators
- 1. UKAEA Northern Research Labs., Springfields (UK)
Description
Creep deformation of Zircaloy cladding in postulated PWR loss-of-coolant accidents may lead to rod-to-rod mechanical interactions. Tests have been performed in the electrically heated FOURSQUARE rig at 7500C and 8500C in steam to investigate this effect. Conservatisms inherent in a simple 'square with rounded corners' coolant channel blockage model have been quantified; about 5-10% flow area may remain even at strains which in ideal circumstances would give total blockage. Reduction of average burst strains produced by an oxide layer (up to 13 μm) has been demonstrated, resulting from strain concentration at oxide cracks. (author)
Additional details
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (UK)
- ISBN
- 0 7277 1306 X
- Imprint Title
- Materials for nuclear reactor core applications. 2 v.
- Imprint Pagination
- 454 p.
- Journal Page Range
- v. 1 p. 79-85.
Conference
- Title
- International conference on materials for nuclear reactor core applications.
- Dates
- 27-29 Oct 1987.
- Place
- Bristol (UK).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 20016527
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCH-SCALE EXPERIMENTS; C CODES; CREEP; DEFORMATION; FLOW BLOCKAGE; FUEL CANS; FUEL RODS; LOSS OF COOLANT; MECHANICAL TESTS; OXIDATION; PWR TYPE REACTORS; STRAINS; VERY HIGH TEMPERATURE; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATERIALS TESTING; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS