FEMAXI-III-computer code for the analysis of fuel behavior by finite element method
- 1. Central Research Inst. of Electric Power Industry, Tokyo (Japan)
Description
It is important to estimate the mechanical fuel behavior, such as pellet clad interaction (PCI) which is closely related to fuel rod failure, in order to improve the efficiency of plant operation by relaxing the restrictions on the operating conditions. Computer code, ''FEMAXI-III'', is newly developed for the analysis of PCI behavior in LWR as the results of cooperative work (JAERI, NFD, Sophia University and CRIEPI). 1) The object of FEMAXI-III code is the analysis of local deformation on fuel rod, related to PCI failure, by the finite element method using the thermal and the mechanical behavior models of pellet and cladding. 2) The performance of FEMAXI-III is verified against the data base obtained from the instrumented fuel assembly irradiated in HBWR (Halden Reactor). Calculated center temperature and diameter change generated in fuel rod during power ramp are in agreement with Halden data. (author)
Additional details
Publishing Information
- Journal Title
- Denryoku Chuo Kenkyusho Hokoku
- Journal Issue
- no.280042
- Series
- Denryoku Chuo Kenkyusho Hokoku.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 14724980
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CREEP; DEFORMATION; F CODES; FINITE ELEMENT METHOD; FUEL CANS; FUEL ELEMENTS; FUEL-CLADDING INTERACTIONS; SIMULATION; TEMPERATURE DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; REACTOR COMPONENTS