Study on reduced-moderation spectrum BWR with an Advanced Recycle System
Creators
- 1. Toshiba Corporation, Isogo Nuclear Engineering Center, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan)
- 2. Gifu University, Mechanical and Systems Engineering Department, 1-1 Yanagido, Gifu, 501-1193 (Japan)
Description
A study is being evolved on neutronic and thermal characteristics of a fast spectrum BWR core with the tight fuel lattice for an innovative fuel cycle system named BARS (BWR with an Advanced Recycle System) aiming at Pu multi-recycling and MA's (Minor Actinides) burning. The BARS core has unique characteristics: its neutron spectrum is very hard through tight fuel lattice with fuel pin gap of 1.3 mm and it has neutron streaming channel to keep negative void reactivity on top of one-third of the fuel bundles. Therefore, the neutronic benchmark tests and the thermal-hydraulic tests were planned to measure void reactivity effects, neutron streaming, and the thermal-hydraulic performance of the tight lattice bundle. Through our core design study and benchmark tests, we will make clear the feasibility of the conceptual design of BARS core. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 10 p.
Conference
- Title
- International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
- Acronym
- Physor 2002
- Dates
- 7-10 Oct 2002
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55004498
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- BWR TYPE REACTORS; FUEL CYCLE; FUEL ELEMENT CLUSTERS; FUEL PINS; NEUTRON SPECTRA; RECYCLING; THERMAL HYDRAULICS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; FUEL ELEMENTS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SPECTRA; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)