Published October 1975
| Version v1
Journal article
Present status of ATR, FBR development
Description
The development of ATR and FBR is proceeding in Japan, to attain efficient utilization of nuclear fuel and to secure future supply of energy. The ATR is capable of operation with natural uranium, and its early realization is expected. The FBR is able to produce more fissile material than its consumption. As the prototype of the ATR, ''Fugen'' is moderated with D2O and cooled with boiling light water, and the output is 165 MWe. It is expected to go critical in 1977. As for the FBR, the experimental ''Joyo'' and the prototype ''Monju'' are under development, and Pu-U mixed oxide is used as the fuel. They are cooled with sodium. The Joyo of 100 MWt will go critical in 1976, while the Monju of 300 MWe is still in design stage. (Mori, K.)
Additional details
Publishing Information
- Journal Title
- Genshiryoku Kogyo
- Journal Volume
- 21
- Journal Issue
- 10
- Series
- Genshiryoku Kogyo.
- Journal Page Range
- 40-46, 53
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 7273672
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- INTERNATIONAL COOPERATION; JAPAN; JATR REACTOR; JOYO REACTOR; MONJU REACTOR; RESEARCH PROGRAMS
- Descriptors DEC
- ASIA; BREEDER REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL 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; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; THERMAL REACTORS; WATER COOLED REACTORS