Status of conceptual safety design study of Japanese sodium-cooled fast reactor
- 1. Japan Atomic Power Co., Tokyo (Japan)
- 2. Japan Nuclear Cycle Development Inst., Oarai Engineering Center, Oarai, Ibaraki (Japan)
- 3. Mitsubishi Heavy Industries, Ltd., Yokohama, Kanagawa (Japan)
Description
In this paper, the current conceptual safety design and related evaluation of Japanese Sodium-cooled Fast Reactor which is studied in the framework of the Feasibility Study (FS) on commercialized Fast Reactor Cycle Systems in Japan are described. The purpose of the safety design is to establish a feasible safety concept of FBR which aims at a sustainable energy source of the next generations. The safety targets and the safety design principle are set aiming at realizing worldwide acceptability of the safety level. The basic safety design concept, which can meet the safety targets, was formulated taking along with the defense-in-depth philosophy as the basic safety design principle. In order to cope with wide range of energy and resource demands, there are some various designs both of oxide and metal fuel for JSFR. Some analytical results of typical design basis events, design extension conditions and core damage frequency estimation show the feasibility of the safety design concept for them. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability
- Imprint Pagination
- [2562 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- International conference on nuclear energy systems for future generation and global sustainability
- Acronym
- GLOBAL 2005
- Dates
- 9-13 Oct 2005
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37044260
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMMERCIALIZATION; DESIGN; DESIGN BASIS ACCIDENTS; FEASIBILITY STUDIES; JAPAN; LMFBR TYPE REACTORS; LOSS OF FLOW; MEETINGS; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; SAFETY ANALYSIS; SODIUM; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; ASIA; BREEDER REACTORS; CALCULATION METHODS; DEVELOPED COUNTRIES; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTOR ACCIDENTS; REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name GL2XX, Paper ID GL221DF.pdf; 8 ref., 4 figs., 1 tab.