Preliminary design of China ITER TBM with helium-cooled and solid breeder concept
Description
ITER will play a very important role in first integrated blanket testing in fusion environment. Some DEMO blanket relevant technologies, such as tritium self-sufficiency, extraction of high-grade heat, design criteria, safety requirements and environmental impacts will be demonstrated in ITER test blanket modules (TBMs). China has planed to develop own-favored ITER TBM modules based on China's fusion energy development strategy and DEMO definition for testing during ITER operation period. He-Cooled Solid Breeder with FS is main stream for the fusion reactor blanket design and has foundation of the world R and D database. The helium-cooled solider pebble bed (HC-SB) concept has been adopted as one of option of China ITERTBM design. The preliminary design and analysis have been carried out recently. (author)
Additional details
Publishing Information
- Imprint Title
- 21. IAEA fusion energy conference. Book of abstracts
- Imprint Pagination
- 226 p.
- Journal Page Range
- p. 187
- Report number
- IAEA-CN--149
Conference
- Title
- 21. IAEA fusion energy conference
- Dates
- 16-21 Oct 2006
- Place
- Chengdu (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37110145
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DESIGN; ENVIRONMENTAL IMPACTS; HEAT; HELIUM; ITER TOKAMAK; OPERATION; SAFETY; SOLIDS; TESTING; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELEMENTS; ENERGY; FLUIDS; GASES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- FT/P5--18