Development of ATR
Description
The Power Reactor and Nuclear Fuel Development Corp. was established in 1967, and has carried out the development of an ATR and FBRs. As the result, the advanced thermal prototype reactor ''Fugen'' was operated at the rated output of 165,000 kW on March 20, 1979, and thereafter, the operation has been continued very smoothly. The design of the demonstration reactor is in progress based on the results of development of ''Fugen''. The ATR is the pressure tube type reactor with heavy water moderation and boiling light water cooling. For the ATR, the uranium fuel enriched with plutonium or slightly enriched uranium fuel is used. The ATR can be operated with any proportion in the combination of these two kinds of fuel, accordingly the plutonium obtained by the reprocessing of the spent fuel from light water reactors and depleted uranium can be utilized effectively, and natural uranium and enriched uranium can be saved. The progress of the construction of ''Fugen'', the outline of the research and development of the ATR, high enriched fuel for reducing the cost of nuclear fuel cycle by raising the burn-up, the development of the demonstration reactor, and the development of FBRs are explained. The things which the PNC has to do are to complete the periodic inspection of ''Fugen'' as scheduled and continue the stable operation, to put the design of the demonstration reactor to the evaluation by users, and to start the construction of the prototype FBR ''Monju'' as early as possible. (Kako, I.)
Additional details
Additional titles
- Subtitle (English)
- Achievements and prospects of commercialization
Publishing Information
- Journal Title
- Gensan Nenji Taikai Gijiroku
- Journal Issue
- no.13
- Series
- Gensan Nenji Taikai Gijiroku.
Conference
- Title
- 13. annual conference of the Japan Atomic Industrial Forum.
- Dates
- 4 - 6 Mar 1980.
- Place
- Tokyo, Japan.
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 13675870
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONSTRUCTION; COOLANT CLEANUP SYSTEMS; ENGINEERING; FUEL ELEMENTS; JATR REACTOR; MONJU REACTOR; PLANNING; REACTOR COOLING SYSTEMS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; LIQUID METAL COOLED REACTORS; NATURAL URANIUM REACTORS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; THERMAL REACTORS; WATER COOLED REACTORS