Experience from a collocated fast reactor fuel cycle
Creators
Description
Experience of the DFR fast reactor operation (in Dunrey, Great Britain) together with the facilities of the external fuel cycle is given. The aim of collocation of the fast reactor and the corresponding mettalurgical, chemical and technical production is to minimize the quantity of the deficite and expensive highly enriched fuel, to simplify the methods of fuel improvement of different enaichment and composition, to obviate the difficulties. The DFR thermal power is 60 MW, the coolant is sodium, the fuel is highly enriched uranium in the form of molybdenum alloy. The technology of fuel production and reprocessing are given in brief. The conclusion is made that although total collocalization of the fuel cycle minimizes fissible material transportations and their debts in the cycle, the sizes of such a nuclear-energy park would be limited by the requirements of the energy system ( 5-6 mln. kW)
Additional details
Additional titles
- Original title (Russian)
- Опыт локализации топливного цикла быстрых реакторов
Publishing Information
- Journal Title
- At. Tekh. Rubezhom
- Journal Issue
- no.4
- Series
- At. Tekh. Rubezhom.
- ISSN
- 0320-9326
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 12585935
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DFR REACTOR; FLOWSHEETS; FUEL CYCLE; FUEL CYCLE CENTERS; FUEL FABRICATION PLANTS; FUEL REPROCESSING PLANTS; SPECIFICATIONS
- Descriptors DEC
- BREEDER REACTORS; DIAGRAMS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; NUCLEAR FACILITIES; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS
Optional Information
- Notes
- Abridged transleted from Nucl. Engin. Intern., v. 24(281) p. 32-35 1979.