KUTIM: An efficient approach for tritium balances in fast breeder and fusion reactors

Journal Article · Sun Oct 01 04:00:00 EDT 1995 · Fusion Technology

OSTI ID:196746

Masse, F; Latge, C ^[1]

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1. French Atomic Energy Commission, Saint-Paul-lez-Durance (France)

One of the critical issues in the development of Breeding Blankets for the Fusion Demonstration Reactor, DEMO, is the tritium control, particularly in the coolant and the tritium extraction system. To be able to understand and model the tritium behaviour and releases through various interfaces, a code is being developed, following the same approach as for Liquid Metal Fast Breeder Reactors (LMFBRs) for which an efficient tool is already available: KUTIM, here described. The new model proposed for fusion purposes will contribute to compare and choose means to reduce the tritium releases and more generally will be a support for design activities for Breeding Blankets. 6 refs., 2 figs., 1 tab.

• OSTI ID: 196746
• Report Number(s): CONF-950506--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 pt 2 Vol. 28; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BREEDER REACTORS
BREEDING BLANKETS
DESIGN
FAST REACTORS
INVENTORIES
LMFBR TYPE REACTORS
MASS BALANCE
NUMERICAL DATA
PHENIX REACTOR
STEAM GENERATORS
THERMONUCLEAR FUELS
THERMONUCLEAR REACTORS
TRITIUM
TRITIUM RECOVERY