Performance analysis and test on the KAERI devised spacer grids for PWRs
Creators
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
Spacer grid which is one of the most important structural components in a pressurized light water reactor fuel assembly supports the fuel rods laterally and vertically. Based on design experiences and by scrutinizing the design features of advanced nuclear fuels and the international patents of spacer grids, KAERI has devised its own spacer grid shapes and acquired patents. In this study, a performance evaluation on two new spacer grid shapes devised by KAERI was carried out from mechanical/structural and thermohydraulic view points. And also a performance evaluation on two commercial spacer grid shapes was carried out for the sake of a comparison. The comparisons included the spring characteristics, fuel rod vibration characteristics, fretting wear resistance, impact strength characteristics, CHF enhancement, and pressure drop level of the spacer grid shapes. The comparison results have shown that the performances of the new spacer grid shapes are better or at least not worse than those of the commercial spacer grid shapes. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Power and Energy Systems
- Journal Volume
- 2
- Journal Issue
- 1
- Journal Page Range
- p. 47-56
- ISSN
- 1881-3062
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39117136
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUGMENTATION; CRITICAL HEAT FLUX; EVALUATION; FRETTING CORROSION; FUEL ASSEMBLIES; FUEL RODS; IMPACT STRENGTH; KAERI; MIXING; PERFORMANCE; PWR TYPE REACTORS; SPACERS; SPRINGS; VANES
- Descriptors DEC
- CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; KOREAN ORGANIZATIONS; MACHINE PARTS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 12 refs., 12 figs., 4 tabs.