Proceedings of the workshop on the cooling of advanced reactors
Creators
- 1. Osaka Univ., Suita (Japan). Faculty of Engineering
Description
Nuclear power has become to meet electric power demand by considerable proportion, and the peaceful utilization of atomic energy steadily returns scientific and technological results to the society. As to the problem of 'Heat removal from high performance nuclear reactors' taken up successively since the last year, there are the problem of heat transport in the reactors of new types as the source of energy supply, especially the pursuit from the viewpoint of the improvement of safety and reliability related to thermal engineering, and regarding nuclear reactors, the problem of the design and operation control of experimental facilities under the utmost condition in the core and its vicinity, not only the problem of reactors proper. Particularly regarding research reactors, precision has become to be demanded in addition to the safety and reliability thermally for various facilities. In the workshop of this year, the presenting of reports and discussion were carried out from the standpoint of thermal engineering on fast reactors and light water reactors of next generation, new research reactors and experimental facilities. (K.I.)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 186 p.
- Report number
- KURRI-TR--344
Conference
- Title
- Workshop on the cooling of advanced reactors.
- Dates
- 18 Jan 1990.
- Place
- Kumatori, Osaka (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22091086
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONVERSION RATIO; CRITICAL HEAT FLUX; HEAT EXCHANGERS; HEAT TRANSFER; HELIUM; HFIR REACTOR; LIQUID METALS; LMFBR TYPE REACTORS; NEUTRON SOURCES; REACTOR ACCIDENTS; SODIUM; SUPERFLUIDITY; TWO-PHASE FLOW; ULTRACOLD NEUTRONS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BARYONS; BREEDER REACTORS; COLD NEUTRONS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; FLUID FLOW; FLUIDS; HADRONS; HEAT FLUX; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; LIQUID METAL COOLED REACTORS; LIQUIDS; METALS; NEUTRONS; NONMETALS; NUCLEONS; PARTICLE SOURCES; RADIATION SOURCES; RARE GASES; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER MODERATED REACTORS