Project information
Research into technologies for high potentional heat transfer from a nuclear source

Project Identification
2A-1TP1/067
Project Period
11/2006 - 12/2010
Investor / Pogramme / Project type
Ministry of Industry and Trade of the CR
MU Faculty or unit
Faculty of Science
Keywords
Nuclear power plant; fast reactor; high temperature reactor; high potentional heat transfer; heat exchangers; reaction of sodium with heat carriers; halide salts; safety; reliability; gas cycle; material for high temperature applications; GIF; 6. RP EU
Cooperating Organization
Energovýzkum, spol. s r.o.

Research into technologies of high potentional heat transfer from a nuclear source, where the nuclear source is considered a fast reactor and/or high temperature reactor cooled by molten salts. In the case the considered nuclear source is a fast reactor (SFR) the project is focused on R&D and design documentation for bids of heat exchangers for reactor of the new generation, denoted as SFR (Sodium Fast Reactor) in the Generation IV. International Forum including basic design documentation. The important objectives is research into conceptional design of heat exchanger with a very high level of safety and reability during future operation at NPPs, where the reactor coolant is the liquid sodium.

Publications

Total number of publications: 3


You are running an old browser version. We recommend updating your browser to its latest version.

More info