Current status of VHTR development in Japan
Journal Article
·
· Am. Soc. Mech. Eng., (Pap.); (United States)
OSTI ID:6758147
As a long-term clean energy system, it has been pointed out for years that direct application of nuclear process heat could be effectively carried out by introduction of the Very High Temperature Reactor (VHTR). Japan Atomic Energy Research Institute has been promoting a research and development program on the experimental VHTR since 1969 for the direct use of reactor process heat. 5 refs.
- Research Organization:
- Jpn At Energy Res Inst, Tokyo
- OSTI ID:
- 6758147
- Journal Information:
- Am. Soc. Mech. Eng., (Pap.); (United States), Vol. 81-WA/NE-9
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
RESEARCH PROGRAMS
JAPAN
HEAT TRANSFER
HELIUM
JAERI
NUCLEAR POWER PLANTS
PROCESS HEAT REACTORS
STEELS
ALLOYS
ASIA
ELEMENTS
ENERGY TRANSFER
FLUIDS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
IRON ALLOYS
IRON BASE ALLOYS
JAPANESE ORGANIZATIONS
NATIONAL ORGANIZATIONS
NONMETALS
NUCLEAR FACILITIES
POWER PLANTS
RARE GASES
REACTORS
THERMAL POWER PLANTS
210300* - Power Reactors
Nonbreeding
Graphite Moderated
210900 - Nuclear Power Plants- Process Heat Reactors- (-1987)
HTGR TYPE REACTORS
RESEARCH PROGRAMS
JAPAN
HEAT TRANSFER
HELIUM
JAERI
NUCLEAR POWER PLANTS
PROCESS HEAT REACTORS
STEELS
ALLOYS
ASIA
ELEMENTS
ENERGY TRANSFER
FLUIDS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
IRON ALLOYS
IRON BASE ALLOYS
JAPANESE ORGANIZATIONS
NATIONAL ORGANIZATIONS
NONMETALS
NUCLEAR FACILITIES
POWER PLANTS
RARE GASES
REACTORS
THERMAL POWER PLANTS
210300* - Power Reactors
Nonbreeding
Graphite Moderated
210900 - Nuclear Power Plants- Process Heat Reactors- (-1987)