ITER enhanced heat flux first wall technology
Creators
- 1. Southwestern Institute of Physics, Chengdu, Sichuan (China)
Description
ITER enhanced heat flux first wall shields extra-high thermal flux from its burning plasma and limit the plasma boundary. With a surface heat load up to 4.7 MW/m2, it uses a profiled surface of Be tiles mounting on the hypovaportron (HVT) cooling structure that composes of Cu Cr Zr alloy and stainless steel. Heat load are being transferred to 4 MPa and 2 m/s cooling water through these well-bonded materials. It is able to withstand the pulse operation of ITER for 15000 cycles. Hot iso-static pressing (HIP) and explosion bonding technologies have been successfully developed to make reliable Be/Cu Cr Zr and Cu Cr Zr/316L (N) joints, respectively. The tensile strength and microstructure of the copper alloy was well controlled by optimizing heat treatment and thermal process. The residual stress of the post-HIP ed Be/Cu Cr Zr joints was reduced significantly by improving the interface layers. The thermal fatigue life of the HVT cooling channel was greatly extended with an innovative design. Full-scale FW finger pairs and a semi-prototype were made, the pairs successfully withstood thermal fatigue test at 4.7 MW/m2 for 7500 cycles and 5.9 MW/m2 for 1500 cycles. The enhanced heat flux technology was thus successfully qualified according to ITER requirements. (authors)
Additional details
Publishing Information
- Publisher
- China Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 978-7-5022-8776-4
- Imprint Title
- Progress report on nuclear science and technology in China (Vol.5). Proceedings of academic annual meeting of China Nuclear Society in 2017, No.7--Nuclear Fusion and Plasma Physics sub-volume
- Imprint Pagination
- 66 p.
- Journal Page Range
- p. 41-48
Conference
- Title
- 2017 academic annual meeting of China Nuclear Society
- Dates
- 16-18 Oct 2017
- Place
- Weihai (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 53102362
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COPPER ALLOYS; FIRST WALL; HEAT TREATMENTS; HEATING LOAD; ITER TOKAMAK; JOINTS; MICROSTRUCTURE; PRESSING; RESIDUAL STRESSES; STAINLESS STEELS; SURFACES; TENSILE PROPERTIES; THERMAL FATIGUE
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; FABRICATION; FATIGUE; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS WORKING; MECHANICAL PROPERTIES; STEELS; STRESSES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 7 figs., 1 tab., 7 refs.