Published September 2000
| Version v1
Journal article
Analysis of PCMI threshold of fuel rod for Qinshan Nuclear Power Plant
Description
The Japanese fuel behavior analysis code FEMAXI-IV provided by OECD is used to calculate the stress level of Qinshan Nuclear Power Plant fuel rod under pellet clad mechanical interaction (PCMI) and to evaluate the safety margin of PCMI. The threshold of rod power is obtained after the determination of threshold of local hoop stress. The safety margin of linear power is 147 W/cm and the safety margin of local hoop stress is 263 MPa under the accident condition of unanticipated control rod withdrawing according to the threshold
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 34
- Journal Issue
- suppl
- Journal Page Range
- p. 86-89
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 32020858
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- F CODES; FUEL RODS; FUEL-CLADDING INTERACTIONS; NUCLEAR POWER PLANTS; OECD; QINSHAN-1 REACTOR; REACTOR SAFETY; STRESS ANALYSIS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; INTERNATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS