Current progress of Chinese HCCB TBM program
Creators
- 1. Southwestern Institute of Physics, Shuang Liu, Chengdu 610225 (China)
Description
Highlights: • China plan to test own test blanket modules (TBM) during ITER different operation phase (H-H,D-D, D-T). • A preliminary design (PD) of HCCB TBM have being performed since 2014. • In order to reduce the effects of magnetic field ripple, the HCCB TBM design has been updated with reduced RAFM mass. • Related R&D on key components fabrication, welding technology, materials development, He test loop constraction and mock-up test of TBM modules and components have being implemented. • The current status on design and related R&D, as well as the development of auxiliary system (TES, CPS,HCS, etc.,) of Chinese HCCB TBS program ware overviewed. - Abstract: ITER is an unique opportunity to test tritium breeding blanket mock-ups in integrated Tokamak operating conditions. Helium-cooled ceramic breeder (HCCB) test blanket module will be the primary option of the Chinese ITER TBM program. China plans to test its own test blanket modules (TBM) during ITER different operation phase (H-H,D-D, D-T). A preliminary design of HCCB TBM have been completed in 2013. In order to reduce the effects of magnetic field ripple, the HCCB TBM design has been updated with reduced RAFM mass recently. Related R&D on key components fabrication, welding technology, materials development and mock-up test of TBM modules and components have being implemented. In this paper, the current status on design and related R&D, as well as the development of auxiliary system (TES, CPS,HCS, etc.,) of Chinese HCCB TBS program were introduced.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2016.02.010Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2016.02.010;
- PII
- S0920-3796(16)30086-2;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part A
- Journal Page Range
- p. 729-735
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 12. international symposium on fusion nuclear technology
- Acronym
- ISFNT-12
- Dates
- 14-18 Sep 2015
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48067813
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY SYSTEMS; BREEDING BLANKETS; CHINA; D-D REACTORS; D-T OPERATION; HELIUM; ITER TOKAMAK; MAGNETIC FIELD RIPPLES; TRITIUM; WELDING
- Descriptors DEC
- ASIA; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; ELEMENTS; FABRICATION; FLUIDS; GASES; HYDROGEN ISOTOPES; ISOTOPES; JOINING; LIGHT NUCLEI; MAGNETIC FIELD CONFIGURATIONS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.