LMFBR coolant system components development in Japan
Creators
Description
A review is made on the major components and the research and developments (R and D) of them in the coolant system of sodium-cooled fast reactors in Japan. Two fast reactors, the experimental fast reactor ''Joyo'' and the prototype fast breeder reactor ''Monju'', are being developed as the national project by the Power Reactor and Nuclear Fuel Development Corporation (PNC). In accordance with the project, design, research and development have been extensively made by PNC itself and industries, including in-sodium and water tests of prototype components, characteristic tests, fabrication tests, etc. for both reactors. ''Joyo'' with initial output of 50 MWt is now in preoperational test, while ''Monju'' with 300 MWe is in the stage of check and review by the governmental authority
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York
- Imprint Title
- 1976 ASME-ANS international conference on advanced nuclear energy systems
- Journal Page Range
- p. 193-213.
Conference
- Title
- ASME-ANS joint international conference on advanced nuclear energy systems.
- Dates
- 13 Mar 1976.
- Place
- Pittsburgh, PA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9379793
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT EXCHANGERS; JOYO REACTOR; MONJU REACTOR; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; SPECIFICATIONS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS
Optional Information
- Notes
- Imprint:See CONF-760303--.