Core and transient design for a BWR of the next century
Creators
- 1. G.E. Nuclear Energy, California (United States)
- 2. Hitachi, Ltd., Hitachi, Ibaraki (Japan)
- 3. Toshiba Corp., Yokohama, Kanagawa (Japan)
- 4. Tokyo Electric Power Co., Inc., Tokyo (Japan)
Description
This paper reports on the progress of studies to establish the core and transient design for a Boiling Water Reactor (BWR) of the next century. A key emphasis for the core and transient design is flexibility in order to address changeable social conditions from the following aspects: Flexibility in operating cycle length. Flexibility in fuel discharge burnup. Flexibility in use of CU2 or MOx fuel. Other key emphases are improvement of operations and maintenance and reduction of plant costs. To address these areas, core design studies investigating potential benefits from alternate fuel assembly sizes and control strategies have been initiated. Means to mitigate the impact of transients are also under investigation in order to provide further improvement in operating margins which might in turn be used to enhance flexibility and reduce plant costs. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 2
- Imprint Pagination
- 512 p.
- Journal Page Range
- p. 803-806
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38019055
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; CONTROL ELEMENTS; CRITICAL HEAT FLUX; DESIGN; FUEL ELEMENT CLUSTERS; MITIGATION; MIXED OXIDE FUELS; POWER DENSITY; REACTOR CORES; REACTOR LATTICE PARAMETERS; TRANSIENTS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; FUELS; HEAT FLUX; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs., 6 figs., 1 tab.