Finite element analysis of BWR fuel channel buckling during a seismic event
- 1. Global Nuclear Fuel - Japan, Co., Ltd., Yokosuka, Kanagawa (Japan)
- 2. Global Nuclear Fuel - Americas, LLC, Wilmington, NC (United States)
Description
This paper documents the predicted response of three BWR fuel channel designs in bending using a typical moment profile for GNF fuel designs. The bending performance of the fuel channel is predicted using ANSYS, a finite element modeling tool. Specifically, linear and non-linear buckling analyses were performed to determine the onset of elastic buckling, which causes a wavy structure on the compression face in bending that might also increase channel – control blade friction, and to determine to onset of channel collapse, which causes permanent deformation and would inhibit control rod insertion. The three channel designs considered in this paper are the 0.080 inch uniform channel, the 0.100 inch uniform channel and the 0.120 inch uniform channel at the beginning of fuel life (BOL) and at the end of fuel life (EOL). (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
- 47079933
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENDING; BWR TYPE REACTORS; DESIGN; DYNAMIC LOADS; FINITE ELEMENT METHOD; FUEL CHANNELS; MATERIALS TESTING; SEISMIC EVENTS; STRAINS; STRESS ANALYSIS; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K
- Descriptors DEC
- CALCULATION METHODS; DEFORMATION; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100114.pdf; 11 figs.