2 edition of Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors found in the catalog.
Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors
Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors (3rd 1976 Tokyo, Japan)
|Contributions||Dōryokuro Kakunenryō Kaihatsu Jigyōdan., OECD Nuclear Energy Agency.|
|LC Classifications||TK9203.L5 S62 1976|
|The Physical Object|
|Pagination||2 v. :|
|LC Control Number||77378662|
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Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors: Tokyo, March [Japan) (3rd: Dsoryokuro Kakunenryso Kaihatsu Jigysodan. ; OECD Nuclear Energy Agency.
Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors Tokyo] on *FREE* shipping on qualifying : Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors Tokyo, Japan) (3rd: Dsoryokuro Kakunenryso Kaihatsu Jigysodan. ; OECD Nuclear Energy Agency. Conference: Second specialist meeting on sodium/fuel interaction in fast reactors, Ispra, Italy, November Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors: Tokyo, March by Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors (Book).
technical report: proceedings of the meeting on special techniques and materials for semiconductor detectors, ispra, italy, octoberproceedings of the meeting on special techniques and materials for semiconductor detectors, ispra, italy, octoberThe main challenge for fuels for future Sodium Fast Reactor systems is the development and qualification of a nuclear fuel sub-assembly which meets the Generation IV International Forum goals.
The Advanced Fuel project investigates high burn-up minor actinide bearing fuels as well as claddings and wrappers to withstand high neutron doses and Cited by: Sodium-cooled reactors could be categorized into two types: loop and pool types (FigureFigure ).
In the loop types, major components in the primary systems are connected by piping. Existing reactors have nozzles on the reactor vessels for the piping.
Some advanced designs eliminate nozzles adopting piping through the by: 4. A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The acronym SFR particularly refers to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), the other based on the metal-fueled integral fast reactor.
Several sodium-cooled fast reactors have been built, some still in. The Sodium Reactor Experiment was a pioneering nuclear power plant built by Atomics International at the Santa Susana Field Laboratory near Simi Valley, reactor operated from to On J the Sodium Reactor Experiment became the first nuclear reactor in the United States to produce electrical power for a commercial power grid by Location: Santa Susana Field Laboratory, California.
The fast transients simulating the ones introduced by the reactor safety Table 1 Burn-up Max max Number of linear Max fluence % H.A.
pins power n/cm2 w/cm Z2 DFR-3 7,2 3 5,8 x 10 22 DFR-4 6,67 3 4,7 x 10 22 DFR-5 5,14 3 9,15 x 10 systems will be investigated in the sec ond installation.
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