紧凑型聚变裂变混合堆自举电流的数值模拟研究

核聚变与等离子体物理 ›› 2015, Vol. 35 ›› Issue (1): 14-18.

紧凑型聚变裂变混合堆自举电流的数值模拟研究

陈美霞，刘成岳，舒双宝

(1. 合肥工业大学电子科学与应用物理学院，合肥 230009； 2. 合肥工业大学仪器科学与光电工程学院，合肥 230009)

收稿日期:2014-07-24 修回日期:2015-01-18 出版日期:2015-03-15 发布日期:2015-03-13
作者简介:陈美霞(1977-)，女，安徽界首人，硕士，实验师，从事聚变反应堆堆芯概念设计及数值模拟。
基金资助:
国家自然科学基金资助项目(11175211，11205194)；中央高校基本科研业务费专项资金资助项目(2013HGXJ0190)

Simulation on bootstrap current for the compact fusion-fission hybrid reactor

CHEN Mei-xia, LIU Cheng-yue, SHU Shuang-bao

(1. School of Electronic Science & Applied Physics, Hefei University of Technology, Hefei 230009； 2. School of Instrument Science and Opto-electronics Engineering, Hefei University of Technology, Hefei 230009)

Received:2014-07-24 Revised:2015-01-18 Online:2015-03-15 Published:2015-03-13

摘要/Abstract

摘要：

以平衡程序Jsolver 为基础开展了紧凑型聚变裂变混合堆先进等离子体平衡位形设计，重点研究了反剪切运行模式，并在此位形下研究了自举电流的计算、分布及份额。

关键词: 紧凑型聚变裂变混合堆, Jsolver, 自举电流, 先进运行模式

Abstract:

On the basis of the equilibrium code Jsolver, the compact fusion-fission hybrid reactor’s advanced equilibrium configuration design is carried out, especially for the reversed shear operation mode. And the calculation, distribution and fraction of bootstrap current are also simulated.

Key words: Compact fusion-fission hybrid reactor, Jsolver, Bootstrap current, Advanced operation mode

中图分类号:

TL61+2

陈美霞，刘成岳，舒双宝. 紧凑型聚变裂变混合堆自举电流的数值模拟研究[J]. 核聚变与等离子体物理, 2015, 35(1): 14-18.

CHEN Mei-xia, LIU Cheng-yue, SHU Shuang-bao. Simulation on bootstrap current for the compact fusion-fission hybrid reactor[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2015, 35(1): 14-18.

参考文献

[1] 邱励俭. 聚变能及其应用 [M]. 北京: 科学出版社,2008. 163.
[2] Jardin S, Menard J, Kessel C, et al. Description of Jsolver V1.3 input file INEQU [R]. Princeton: PPPL, 1999.
[3] Chu D L, Wu B, Wu Y C, et al. Preliminary analysis of advanced equilibrium configuration for the fusion-driven subcritical system [J]. Plasma Science and Technology,2003, 5(6): 2085−2092.
[4] Wu Bin. Introduction of fusion driven subcritical system plasma design [J]. Fusion Engineering and Design, 2003,66−68: 181−186.
[5] 吴斌. HT-7U 超导托卡马克装置的放电模拟研究 [D].合肥: 中国科学院等离子体物理研究所, 2002.
[6] Wan B N, Li J G, Wu Y C, et al. Progress in technology and experiment of superconducting tokamaks in ASIPP[J]. Fusion Engineering and Design, 2010, 85: 1048–1053.
[7] Tobita K, Nishio S, Sato M, et al. Concept of compact low aspect ratio demo rector, slim CS [A]. 21th IAEA Fusion Energy Conference [C]. Chengdu, 2006. 16−22.
[8] 陈美霞, 吴斌, 周晓林, 等. 紧凑型聚变裂变混合堆参数优化及数值模拟 [J]. 核聚变与等离子体物理, 2008,28(3): 247−251.
[9] Nishio S, Ushigusa K. Conceptual design of advanced steady-state tokamak reactor [A]. 18th IAEA Fusion Energy Conference[C]. Sorrento, Italy, 2000. 4−10.
[10] Zohm H, Angioni C, Fable E, et al. On the physics guidelines for a tokamak DEMO [J]. Nucl. Fusion, 2013,53(7): 3019−3025.
[11] Simonin A, H de Esch, Doceul L, et al. Conceptual design of a high-voltage compact bushing for application to future N-NBI systems of fusion reactors [J]. Fusion Engineering and Design, 2013, 88: 1–7.
[12] ITER EDA documentation. Summary ITER final design report [R]. GA0FDR2 01−12−19 W0.1, 2001.
[13] John Wesson. Tokamaks. [M] New York: Oxford University Press, Inc., 1997. 166−168.
[14] 张一鸣, 曾丽萍, 沈欣媛, 等. ITER 计划与聚变能发展战略[J]. 核聚变与等离子体物理, 2013, 33(4): 359−365.
[15] Allen H Boozer. Stellarators and the path from ITER to DEMO [J] .Plasma Phys. Contr. Fusion, 2008, 50(12):4005−4022.
[16] 陈美霞, 刘成岳, 吴斌. 紧凑型聚变裂变混合堆先进运行模式的数值模拟 [J]. 核聚变与等离子体物理,2012, 32(4): 323−327.
[17] 李昊, 吴斌, 王进芳, 等. EAST 4MW 中性束注入放电模拟研究 [J]. 核聚变与等离子体物理, 2014, 34(1): 57−62.