Published 2005 | Version v1
Computer medium

Advanced metal fuel core design study for SFR in the 'feasibility study' in Japan

  • 1. Japan Nuclear Cycle Development Inst., Oarai Engineering Center, Oarai, Ibaraki (Japan)

Description

A sodium cooled metal fuel fast reactor core design study was performed. The proposed new core concept is characterized by single Pu-enrichment and 2 radial regions with differing heavy metal density metal fuels. The core had the potential to achieve an outlet temperature of 550degC while taking into account the fuel/cladding compatibility concerns. The breeding ratio of the core reached 1.0 without blanket fuel. These results show the potential for a capability of sodium cooled metal fuel core to be one of the attractive fast reactor core concepts for the future. (author)

Part of:
GLOBAL 2005: Proceedings of the international conference on nuclear energy systems for future generation and global sustainability

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)

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 GL3XX, Paper ID GL399DF.pdf; 8 refs., 4 figs., 4 tabs.