Design status and development strategy of China liquid lithium–lead blankets and related material technology
Source abstract
Abstract
Abstract A series of fusion reactors (named FDS series) have been designed and assessed in China, with four types of liquid lithium lead blankets including the RAFM steel-structured He-cooled quasi-static LiPb tritium breeder (SLL) blanket, the RAFM steel-structured He–LiPb dual-cooled (DLL) blanket, the RAFM steel-structured refractory material thermally-insulated high temperature LiPb (HTL) hydrogen production blanket and the RAFM steel or optionally the austenitic stainless steel-structured He–LiPb dual-cooled high level waste transmutation (DWT) blanket. To demonstrate and validate the feasibility of the candidate blankets for fusion energy application, the three-phases-strategy of TBM (test blanket module) development, i.e. material R&D and out-of-pile experimental mockup, EAST-TBM and ITER-TBM have been proposed. A brief overview of the four types of LiPb blanket designs and their goals are given. Material technology requirement and development strategy are also presented in this paper.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Magnetic confinement fusion research
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (13)
Show source-provided references
1. Wu · Fus. Eng. Des. · 2006 · 81 · 271310.1016/j.fusengdes.2006.07.068 ↗
2. Wu · Plasma Sci. Technol. · 2001 · 3 · 108510.1088/1009-0630/3/6/011 ↗
3. Wu · J. Nucl. Mater. · 2002 · 307–311 · 162910.1016/S0022-3115(02)01272-2 ↗
4. Wu · Fus. Eng. Des. · 2006 · 81 · 130510.1016/j.fusengdes.2005.10.015 ↗
5. Wu · Chinese J. Nucl. Sci. Eng. · 2005 · 25 · 76
6. H. Chen, Y. Wu, in: The 21st International Atomic Energy Agency Fusion Energy Conference, 16–20 October, 2006, Chendu, China.
7. N. Baluc et al., J. Nucl. Mater., in press, doi:10.1016/j.jnucmat.2007.03.036.10.1016/j.jnucmat.2007.03.036 ↗
8. C.P.C. Wong et al., J. Nucl. Mater., in press, doi:10.1016/j.jnucmat.2007.03.241.10.1016/j.jnucmat.2007.03.241 ↗
9. Y. Wu, W. Wang, S. Liu, H. Chen, S. Zheng, Y. Bai, et al., Design description document for the Chinese dual-functional lithium lead-test blanket module for ITER, 2005.
10. Y. Wu, the FDS Team, in: The 21st International Atomic Energy Agency Fusion Energy Conference, 16–20 October, 2006, Chendu, China, Nucl. Fus., to be published.
11. Q. Huang et al., J. Nucl. Mater., in press, doi:10.1016/j.jnucmat.2007.03.153.10.1016/j.jnucmat.2007.03.153 ↗
12. Li · J. Nucl. Mater. · 2004 · 329–333 · 140710.1016/j.jnucmat.2004.04.207 ↗
13. Q. Huang, Y. Wu, C. Li, Y. Li, Y. Feng, M. Zhang, L. Peng, Q. Li, in: Proceedings of the 8th China–Japan Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering, 4–8 October, 2004, Sendai, Japan.