Published August 1985
| Version v1
Journal article
Neutronics calculations of the INTOR blanket with austenitic steel as structural material and low-Z coating
Creators
- 1. Comissao Nacional de Energia Nuclear de Brasil, Rio de Janeiro
Description
Some characteristics of the first generation of fusion Experimental Power Reactors (EPR), such as a low-Z first wall coating and austenitic steel as structural material, are investigated when they are implemented for the INTOR blanket. Neutronic analysis was carried out to study the feasibility of those features to INTOR. So, the tritium breeding ratio, the nuclear heating, and the gas production inside the structural material were calculated to analyze the performance of the blanket. Graphite and beryllium are used as the first-wall coating material. (orig.)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Mater.
- Journal Volume
- 133/134
- Series
- J. Nucl. Mater.
- Journal Page Range
- 858-860
- ISSN
- 0022-3115
- CODEN
- JNUMA
Conference
- Title
- 1. international conference on fusion reactor materials (ICFRM-1).
- Dates
- 3-6 Dec 1984.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17014468
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BERYLLIUM; BREEDING RATIO; COATINGS; ENERGY SPECTRA; FIRST WALL; GRAPHITE; HELIUM; HYDROGEN GENERATION; INTOR TOKAMAK; NEUTRON SOURCES; RESPONSE FUNCTIONS; THEORETICAL DATA; THERMONUCLEAR REACTOR MATERIAL; THICKNESS; TRITIUM RECOVERY
- Descriptors DEC
- ALKALINE EARTH METALS; CARBON; CLOSED PLASMA DEVICES; CONVERSION RATIO; DATA; DIMENSIONS; ELEMENTS; FUNCTIONS; INFORMATION; MATERIALS; METALS; NONMETALS; NUMERICAL DATA; PARTICLE SOURCES; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; RADIATION SOURCES; RARE GASES; SPECTRA; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TOKAMAK DEVICES