Criteria for removal of defective fuel rod from fuel assembly under repair without cladding rupture
- 1. SRC RF TRINITI, Moscow (Russian Federation)
Description
During repair of a failed fuel assembly (FA) there is a risk of cladding rupture while a defective fuel rod is forced out of the assembly skeleton. To reduce the corresponding risks, a program of experimental and analytical studies for WWER fuel was performed. It resulted in formulation of criteria for successful removal of the defective fuel rod from the FA under repair. 'Successful' means that no cladding rupture occurs. The paper summarizes the available data of post-irradiation examinations of WWER FAs with leaking fuel rods. A technique for express estimation of hydrogen content in cladding of a defective fuel rod is presented. The degradation of cladding mechanical properties can be estimated with this technique as well. A criterion of severe secondary hydriding involved in the risk analysis is also discussed. Finally, it is shown how the information on operation conditions may be used for prompt evaluation of the limiting force for successful removal of a defective fuel rod during FA repair in the inspection stand. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting (WRFPM 2014)
- Imprint Pagination
- 784 p.
- Journal Page Range
- 6 p.
Conference
- Title
- 2014 water reactor fuel performance meeting/ top fuel / LWR fuel performance meeting
- Acronym
- WRFPM 2014
- Dates
- 14-17 Sep 2014
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47079913
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BLISTERS; BURNUP; CLADDING; COMPUTER CODES; ELONGATION; EMBRITTLEMENT; FUEL ASSEMBLIES; FUEL RODS; HYDRIDATION; HYDRIDES; HYDROGEN; POST-IRRADIATION EXAMINATION; THERMAL DEGRADATION; WWER TYPE REACTORS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; DEFORMATION; DEPOSITION; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; NONMETALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100073.pdf; 9 refs., 4 figs.