Third SCIP modeling workshop. Beneficial impact of slow power ramp on PCI performance
- 1. AREVA Inc., Charlotte, NC (United States)
- 2. CIEMAT, Madrid (Spain)
- 3. Studsvik Nuclear AB, Nyköping (Sweden)
Description
The paper presents the Third SCIP Modeling Workshop (MWS) that was organized to investigate the PCI mitigating effects of lowering the ramp rate. To that end, the Super Ramp-Extension BWR low ramp-rate subprogram of Studsvik's International Super-Ramp (SR) Program, comprising 8 tests, was used together with a set of SCIP single-step and staircase ramps. The modeling exercise was joined by 11 participants using 10 fuel performance codes from industry, research and regulatory organizations. The paper succinctly presents both the areas where reasonable agreement was achieved, as well as the more important differences. Especially, the predicted cladding stresses have been found to differ significantly and some fuel code groupings were identified. Preliminary conclusions are succinctly presented, the highlight being that pure mechanical effects do not seem to fully explain the slow ramps' benefits - the competition between the oxide formation and healing and the SCC-aggressive agent chemical attack could be an important dynamic factor contributing to slow ramp benefits. (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
- 9 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
- 47070645
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; CRACKS; FISSION PRODUCT RELEASE; FUEL CANS; FUEL ELEMENT FAILURE; FUEL INTEGRITY; FUEL PELLETS; FUEL RODS; FUEL-CLADDING INTERACTIONS; POWER; STRAINS; STRESS CORROSION; STRESSES
- Descriptors DEC
- CHEMICAL REACTIONS; CORROSION; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; PELLETS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: fullpaper100045.pdf; 21 refs., 9 figs., 2 tabs.