|
[1] WAN Y. Design
and strategy for the Chinese fusion engineering testing reactor (CFETR) [C].
San Francisco: SOFE, 2013.
[2] 吴晶, 谌继明, 王平怀, 等. 管道连接装配型ITER增强热负荷第一壁的热工水力分析 [J]. 核聚变与等离子体物理, 2022, 42(1): 28-34.
[3] WAN Y, LI J G, LIU Y, et al.
Overview of the present progress and activities on the CFETR [J]. Nuclear
Fusion, 2017, 57(10): 102009.
[4] YAO D M, BAO L M, LI J G, et
al. Design, analysis and R&D of the EAST
In-Vessel components [J]. Plasma Science and Technology, 2008, 10(3): 367-372.
[5] YAO D M, LI J G, SONG Y T, et
al. EAST in-vessel components design [J]. Fusion
Engineering and Design, 2005, 75: 491-494.
[6] SHERLOCK P, PEACOCK A T, RÖDIG
M. Consolidation of HIP bonding technologies for the ITER first wall
panels [J]. Fusion Engineering and Design, 2007, 82(15-24): 1806-1812.
[7] XU Y, XIE C Y, QIN S G, et al. Preliminary R&D on flat-type W/Cu
plasma-facing materials and components for experimental advanced
superconducting tokamak [J]. Physica Scripta, 2014, 2014(T159): 014008.
[8] LEE W D, KIM K S, SHIN I K, et
al. Preliminary analysis for thermal-fatigue test of HIP joined W and ferritic-
martensitic steel mockup [J]. Fusion Engineering and Design, 2015, 98: 1353-1356.
[9] 魏川子, 宋云涛, 雷明准. CFTER包层第一壁热工水力分析 [J]. 核聚变与等离子体物理, 2016, 36(1): 65- 70.
[10] 刘健, 赖春林, 王金, 等. HL-2M装置第一壁传热结构设计及传热性能测试 [J]. 核聚变与等离子体物理, 2021, 41(1): 33-36.
[11] SONG Y T, YAO D M, WU S T, et
al. Thermal and mechanical analysis of the EAST plasma facing components [J].
Fusion Engineering and Design. 2005, 75: 499-503.
[12] ITER Structural Design Criteria for In-vessel Components [Z]. ITER_D_222RHC V3.0 Standard.
[13] 刘倩雯. CFETR氦冷固态包层第一壁设计优化与瞬态热工安全分析 [D]. 合肥: 中国科学技术大学, 2015. |
