文档介绍：第卷增刊原子能科学技术琒.
200912B Science and Dec2009
聚变一裂变混合堆水冷包层
中子物理性能研究
徐红,杨永伟,周志伟
(100084)
摘要:研究真接应用围际热核聚变实验堆规模的聚变堆作为中子驱动源。采用天然铀为初装核
燃料,并采用现有压水堆核电厂成熟的轻水慢化和冷却技术,设计聚变一裂变混合堆裂变及产氚包层的
MCNPOrigen2
数、氚增殖比、能量放大系数和外中子源效率等中子物理性能的影响。计算分析结果显示,现有核电厂
广泛使用的巳剂弦约跋乱淮驯涠淹萍霾捎玫腢蚒。。等高性能陶瓷及合金核燃料
作为水冷包层的核燃料。都能满足以产能发电为设计目标的新型聚变一裂变混合堆能量放大倍数的设计
要求,但只有和!“,燃料『司时满足聚变燃料氚的生产与消耗自持的要求。研究结果对进一步研
发满足未来核能町持续发展的新型聚变一裂变混合堆技术具有潜在参考价值。
关键词:聚变一裂变混合堆;水冷包层;核燃料;中子物理性能
TL324A10006931(2009)S0-009706
Neutron Characteristics Light Water Blanket
FusionFission Reactor
, YongweiZHOUZhiwei+
Nuclear and New 。 UniversityBeijing,
: feasibility was studied application —
Thermonuclear Reactor)scale nuclear reactor driving neutron
a new power reactor and its tritium produ
cingnuclearfission 瑆 can cooperate the loading natural ura
fuels initial and light water and cooling
current PWRsNumerical the
and Origen2 was performed investigate the different
nuclear fuels neutron characteristics the blanketsuch the effective
neutron multiplying 瑃 tritium 瑃 amplifier and the
effectiveness the driving neutronsThecalculation results U02
收稿日期:——;修回日期:——
作者简介:徐红,男,重庆人,硕士研究生。核能科学与工程专业
*Emailzhouzhw@
原子能科学技术第卷
current nuclear power plantsthe performance ,,
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