Published December 1992
| Version v1
Journal article
Neutronics design and study of the water cooled fast fission blanket of hybrid reactor
- 1. Institute of Applied Physics and Computational Mathematics, Beijing, BJ (China)
Description
The one and two dimensional design and study of the water cooled pebble-bed fast fission blanket neutronics of hybrid reactor have been carried out on the basis of the plasma parameters and core structure of International Thermonuclear Experimental Reactor. The contract between hybrid reactor and fusion reactor has been conducted. The results show that the hybrid reactor as early application of fusion energy is necessary and possible
Additional details
Publishing Information
- Journal Title
- Chinese Journal of Nuclear Science and Engineering
- Journal Volume
- 12
- Journal Issue
- 4
- Journal Page Range
- p. 337-344.
- ISSN
- 0258-0918
- CODEN
- HYGODG
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 25030054
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; BREEDING RATIO; DESIGN; FEASIBILITY STUDIES; FIRST WALL; HYBRID REACTORS; NEUTRON FLUX; ONE-DIMENSIONAL CALCULATIONS; PLUTONIUM; THERMONUCLEAR REACTORS; TRITIUM; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CONVERSION RATIO; ELEMENTS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; METALS; NUCLEI; ODD-EVEN NUCLEI; RADIATION FLUX; RADIOISOTOPES; THERMONUCLEAR REACTOR WALLS; TRANSURANIUM ELEMENTS; YEARS LIVING RADIOISOTOPES