第30卷第1期 2010年3月
核科学与工程
Chincse Journal of Nuclear Science and Engineering
Vol.30
No.1
Mar.
2010
聚变裂变混合发电堆水冷包层中子学设计分析蒋洁琼1.2，王明煌1.2，陈忠1.2，邱岳峰1.2，刘金超1.2，吴宜灿1.2,FDS团队1.2
（1.中国科学院等离子体物理研究所，安徽合肥230031； 2.中国科学技术大学核科学技术学院，安徽合肥230027）
摘要：主要针对案变裂变混合发电堆FDS-EM水冷包层的能量倍增因子M和氯增殖率TBR等中子学参数进行优化计算。FDS-EM包层主要设计目标是在氯自持的基础上获得约1GW的电功率，并且尽可能长时间连续运行不换料。通过初步设计分析给出一个使用核废料（压水堆卸出的废料环、铜系加上贫)作为裂变燃料，能够实现氟自持、能量倍增因子约为90等设计目标，且连续运行至少10年不换料的中子学方案。
关键调：聚变：包层；混合堆；中子学
中图分类号：TL61.3
文献标志码：A
文章编号：0258-0918(2010)01-0070-07
Neutronics design and analysis of water-cooled energy production blanket for a fusion-fission hybrid reactor
JIANG Jie-qiong", WANG Ming-huang', CHEN Zhong'-, QIU Yue-feng*,
LIU Jin-chaol., WU Yi-can'-2, FDS Team'.2
(1. Institute of Plasma Physies, Chinese Academy of Sciences, Hefei of Anhui Prov, 230031, China: 2. School of Nuclear Secience and Technology, University of Science and Technology of China,
Hefei of Anhui Prov, 230027, China)
Abstract;Neutronics calculations were performed to analysis the parameters of blanket energy multiplication factor (M) and tritium breeding ratio (TBR) in a fusion-fission hybrid reactor for energy production named FDS-EM (Energy Multiplier) blanket. The most significant and main goal of the water-cooled FDS-EM blanket is to achieve the energy gain of about 1 GW with self-sustaining tritium, which can operate for as long as possible without fuel unloading and reloading. The preliminarily designed neutronics parameters for FDS-EM were presented, which show that the blanket loaded with the Nuclear Waste (transuranic from 33 o00 MWD/MTU PWR and depleted uranium) for energy multiplication (M 90) with tritium self-sufficiency can operate for at least
收稿日期：2009-06-30；修回日期：2010-02-05
基金项目：中科院知识创新工程重要方向项目：中科院重大科学装备；ITER计划专项项日
作者简介：蒋清琼(1980—)，女，安徽人，博士生，现从事反应堆中子物理学设计研究 70