Published December 1995
| Version v1
Journal article
Neutronics issues in fusion-fission hybrid reactor design
Creators
- 1. Institute of Applied Physics and Computational Mathematics, Beijing, BJ (China)
Description
The coupled neutron and γ-ray transport equations and nuclear number density equations, and its computer program systems concerned in fusion-fission hybrid reactor design are briefly described. The current status and focal point for coming work of nuclear data used in fusion reactor design are explained
Additional details
Publishing Information
- Journal Title
- Trends in Nuclear Physics
- Journal Volume
- 12
- Journal Issue
- 4
- Journal Page Range
- p. 57, 61-63.
- ISSN
- 1003-9988
- CODEN
- HEDOEW
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 27031835
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COMPUTER CODES; DATA; DATA BASE MANAGEMENT; DESIGN; FISSION; GAMMA TRANSPORT THEORY; HYBRID REACTORS; NEUTRON TRANSPORT THEORY; THERMONUCLEAR REACTIONS
- Descriptors DEC
- INFORMATION; MANAGEMENT; NUCLEAR REACTIONS; NUCLEOSYNTHESIS; SYNTHESIS; TRANSPORT THEORY