Behavior of fuel rods owing to baffle jet in Mihama No. 1 reactor and method of evaluating momentum flux
Description
This test was carried out from October, 1977, to May, 1978, by the request of Japan Atomic Energy Research Institute, and it was planned to confirm the fact that the break of fuel rods and grid springs occurred in PWR power stations was caused by baffle jet. It was found that damaged fuel rods were all placed at the position adjacent to the joint of core baffles and exposed directly to the jet flow from the joint. It was concluded from the experiment and the analysis that the cause of the failure of fuel rods is the abnormal vibration of the fuel rods due to the lateral baffle jet flow through the gap of baffle plate joint. In this test, the size of joint gap, the pressure difference at the both ends of the gap, and the axial distribution of the pressure difference were variously changed, and the vibration of fuel rods was measured. The test conditions were decided so as to simulate the actual reactor conditions in Mihama No. 1 reactor. The vibration of fuel rods was continued for about 50 hours, and the failure of the fuel rods and springs was examined. The testing apparatus and testing method, the test results, and the method of evaluating momentum flux are described. (Kako, I.)
Files
Additional details
Publishing Information
- Imprint Title
- Research report on fuel failure in Mihama Unit 1 nuclear power plant
- Journal Page Range
- p. 31-45.
- Report number
- KURRI-TR--197
Conference
- Title
- Study meeting on fuel failure in Mihama Unit 1 nuclear power plant.
- Dates
- 29 Nov 1978.
- Place
- Kumatori, Osaka, Japan.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13645669
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; FLUID FLOW; FUEL ASSEMBLIES; FUEL ELEMENT FAILURE; FUEL RODS; HYDRODYNAMICS; JETS; MECHANICAL TESTS; MECHANICAL VIBRATIONS; MIHAMA-1 REACTOR; REACTOR COOLING SYSTEMS; REACTOR CORES; SHOT PEENING; SPRINGS
- Descriptors DEC
- ACCIDENTS; COLD WORKING; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; FABRICATION; FLUID MECHANICS; FUEL ELEMENTS; INFORMATION; MACHINE PARTS; MATERIALS TESTING; MATERIALS WORKING; MECHANICS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SURFACE TREATMENTS; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS