聚变驱动次临界堆概念设计研究Conceptual design study on the fusion-driven sub-critical system
吴宜灿,柯严,郑善良,汪卫华,储德林,黄群英,刘晓平,许德政,王红艳,黄德所,朱晓翔,高纯静,李静惊,陈义学,吴斌,汪太平,柏云清,章毛连,刘松林,罗月童,刘萍,李春京,李强,童莉莉,翁晓毅,吴磊,王祥科,FDS课题组
摘要(Abstract):
在深入分析相关领域研究发展状况的基础上,提出一个可实现核废料嬗变、可裂变重金属核燃料和氚核燃料增殖、产能等多种功能的次临界反应堆概念。概念有托卡马克实验装置参数适量外推的等离子体物理和技术水平的聚变堆芯、高压He气/液态LiPb双冷却系统嬗变包层。介绍了系统基本概况和参考结构形式,阐述了系统聚变等离子体物理学、包层中子物理学和包层热工水力学设计的基本原则和主要工程约束限制条件,指出系统相关的安全和潜在环境影响问题,给出典型的参考设计参数。
关键词(KeyWords): 聚变;次临界堆;概念设计
基金项目(Foundation): 国家自然科学基金(10175067,10175068,10375067,19385004,19985004);; 中科院知识创新工程;; “百人计划”项目
作者(Author): 吴宜灿,柯严,郑善良,汪卫华,储德林,黄群英,刘晓平,许德政,王红艳,黄德所,朱晓翔,高纯静,李静惊,陈义学,吴斌,汪太平,柏云清,章毛连,刘松林,罗月童,刘萍,李春京,李强,童莉莉,翁晓毅,吴磊,王祥科,FDS课题组
参考文献(References):
- [1] 吴宜灿,邱励俭.聚变中子源驱动的次临界清洁核能系统--聚变能技术的早期应用途径[J].核技术,2000,23(8) :519~525.
- [2] Wu Y C,Qian J P, Yu J N. The Fusion-Driven Hybrid System and its Material Selection[J]. Journal of Nuclear Materials, 2002, 307~311: 1629~1636.
- [3] WU Yican. Progress in Fusion-Driven Hybrid System Studies in China[J]. Fusion Eng. Design, 2002, 63~64:73~78.
- [4] Wu Y C, Zhu X X, Zheng S L, et al. Neutronics Analysis of Dual-cooled Waste Transmutation Blanket for the FDS[J]. Fusion Eng. Design, 2002,63~64: 133~138.
- [5] Ke Y, Wang H Y, Wu Y C. Thermal-hydraulic Analysis of the Dual-cooled Waste Transmutation Blanket for the FDS[J]. Fusion Eng. Design, 2002,61~62: 455~459.
- [6] Wang Hong-yan, Wu Yi-can, He Xiao-xiong. Preliminary Analysis of Liquid Metal MHD Pressure Drop in the Blanket for the FDS[J]. Plasma Physics and Technology, 2002, 4 (5) .
- [7] Zheng Shan-liang, Wu Yi-can. Neutronics Optimization of LiPb-He Dual-cooled Fuel Breeding Blanket for the FDS[J]. Plasma Physics and Technology, 2002,4(4) .
- [8] Zheng Shan-liang, Wu Yi-can, Huang Qun-ying, Neutronics Optimization of Tritium Breeding Blanket for the FDS[J].Plasma Physics and Technology, 2002,4(2) .
- [9] Wang Weihua, Wu Yi can, Ke Yan, et al. Analysis on Stress Field of the Dual-cooled Waste Transmutation Blanket for the FDS[J]. Fusion Engineering and Design, 2003, 69: 297~301.
- [10] Ke Y, Wang H Y, Wu Y C. MHD Simulation of the Liquid Metal/Helium Gas Dual-cooled Waste Transmutation Blanket for FDS[J]. Fusion Engineering and Design, 2003, 69: 431~435.
- [11] ITER: Study of Options for the Reduced Technical Objectives/Reduced Cost (RTO/RC) ITER. ITER-FEAT Outline Design Report[C]. Tokyo, 2000.
- [12] Wan Yuanki, HT-7U Team. Overview of steady state operation of HT-7 and present status of the HT-7U project[J]. Nuclear Fusion, 40 (6) .
- [13] Lee G S, Kim J, Hwang S M, et al. The KSTAR project: An advanced steady state superconducting tokamak experiment[J]. Nuclear Fusion, 40(3Y).
- [14] 储德林,吴斌,黄德所,等.聚变驱动次临界堆聚变堆芯物理设计与分析[J].核科学与工程,2004,24(1) .
- [15] 黄群英,郁金南,万发荣,等.聚变堆低活化马氏体钢发展综述[J].核科学与工程,2004,24(1) .
- [16] 柯严,吴宜灿,王红艳,等.聚变驱动次临界堆双冷嬗变包层结构设计与分析[J].核科学与工程,2004,24(1) .
- [17] 汪卫华,吴宜灿,王红艳,等.聚变驱动次临界堆双冷嬗变包层热工水力学参数设计与分析[J].核科学与工程,2004,24(1) .