【作者】 马续波；

【导师】 陆道纲； 陈义学；

【作者基本信息】 华北电力大学 ， 核反应堆物理与屏蔽， 2012， 博士

【摘要】 根据根据我国核电的中长期发展规划,2020年我国核电的总装机容量达到70GW左右。核电的大规模发展,也面临核燃料供应以及核安全问题。聚变-裂变混合堆由于利用的是(DT)聚变产生的14MeV的高能中子,因此它在增殖核燃料、嬗变核废料方面具有独特优势。同时考虑聚变-裂变混合堆的优势以及我国核电大发展过程中面临的核燃料供应和核废料处理问题,提出了聚变-裂变混合堆压水堆联合循环系统的概念。本论文的主要内容为：(1)开发和完善了BISONC数据库制作软件程序并制作了175群BISONC输运库和燃耗库,并做了初步的验证。开发了聚变裂变混合堆压水堆联合循环系统的中子学分析软件NFFP(Neutronics calculation for fusion-fission hybrid and PWR combined fuel cycle system)。在此软件基础上对该系统的进行了较详细的物理特性分析。(2)根据多目标优化理论和实现方法,对聚变-裂变混合堆包层设计中的功率展平问题进行了理论分析,利用该理论实现了一种直接利用乏燃料进行发电的聚变裂变混合堆包层以及MA嬗变钍基包层概念设计。计算结果表明,功率展平后的包层的功率不均匀系数更小,安全性更好；且包层中燃料区的能量输出要比不展平情况下的能量输出高出约21.7%,因此考虑展平后的包层设计经济性更好,降低了工程技术难度。(3)通过对比分析国内外MOX燃料组件的形式,并根据聚变裂变混合堆增殖燃料的特点,通过对比分析,创新性的提出了适用于聚变裂变混合堆的混合堆增殖燃料组件形式,并对压水堆装载30%HB-MOX燃料的堆芯物理特性进行了研究。对影响反应堆安全的几个重要参数,如燃料和慢化剂温度系数、硼微分价值、缓发中子份额以及停堆裕量等进行了研究,结果表明：慢化剂温度系数和燃料温度系数在整个寿期内都是负的,有利于反应堆的安全。硼微分价值在整个寿期都是负值,但全铀堆芯要比30%HB-MOX燃料堆芯更负,主要原因是能谱更软。装载30%HB-MOX燃料的堆芯寿期末的缓发中子份额为0.508,反应堆停堆裕量和温度系数都满足现行压水堆设计准则。(4)基于成熟的铀钚循环技术,对压水堆装载MOX燃料对我国天然铀资源和燃料制造能力的影响,核电站产生的乏燃料量,分离钚产生量以及使用等问题进行了分析。在假设2040年聚变-裂变混合堆进入我国核燃料循环体系的情况下,分析了对天然铀资源需求的影响以及分离Pu累积累的大小。对Pu的循环使用以及分离Pu的累积量随时间的变化也进行了较详细的分析。根据分析结果给出了建议。本文首次对聚变-裂变混合堆压水堆联合循环系统的物理特性进行了详细的研究,该研究对我国核能的可持续发展具有重要意义。更多还原

【Abstract】 According to China’s nuclear power long-term development plan, in2020China’s total installed nuclear power capacity will be about70GW. With large-scale development of nuclear power, China also faces the problem of nuclear fuel supply and nuclear safety. Fusion-fission hybrid reactor is due to the use of14MeV high-energy neutrons which come from (DT) fusion, so it has unique advantage in producing nuclear fuel and transmutation of nuclear waste. Taking into account the advantages of fusion-fission hybrid reactor and problems of nuclear fuel supply and nuclear waste disposal, fusion-fission hybrid reactor and pressurized water reactor combined fuel cycle system concept was proposed. The main content of this thises is in the following:Development and production of improved BISONC database software program and produced a175group database BISONC transport and fuel consumption database library, and do a preliminary validation. The development of fusion-fission hybrid reactor neutron PWR combined cycle system analysis software NFFP (Neutronics calculation software for fusion-fission hybrid and PWR combined fuel cycle system). This software is based on the system for a more detailed physical characterization.(1) The program for production BISONC transport lib and burnup lib was developed, and three critical benchmark was calculated using the lib. Neutronics calculation software for fusion-fission hybrid and PWR combined fuel cycle system (NFFP)was developed.Based on this software package, the physical characterization of the system was detailed.(2) To deal with the problem large power density variation in the radial deviation in the blanket, power flattening theory was proposed. A generating electricity blanket concept using the PWR spent fuel directly was researched based on the power flattening theory, which was based on ITER parameter level achieve.The results show that the peak-to-average power factor becomes less than no power flattening, and the output power of the fuel zone raises more than21.7%. So, Powe flattening for blanket design becomes more economy, and lower engineering and technical demand comparing with no power flattening blanket design. (3) How to use the fusion-fission hybrid breeding fuel in the PWR is also a key technical problem in the system. The feasibility of using the fusion-fission hybrid breeding fuel in PWR were discussed. Preliminary study was focusing on the physics of using fusion-fission hybrid breeding fuel in the main reactor type Ⅱ plus in China. Key parameters including reactor fuel temperature coefficient, moderator temperature coefficient, boron differential value of the reactor power and other parameters were analyzed in detail. The mixed thorium-based reactor fuel assemblies studies had been performed, and results shown that the features of fusion-fission breeding thorium-based similar to uranium fuel assemblies. Moreover, the component of MA in the fusion-fission hybrid breeding thorium-based fuel were significantly reduced, thereby reducing the likelihood of nuclear proliferation.(4)Based on the mature uranium-plutonium cycle technology, PWR loading MOX fuel was studied. natural uranium resources, our manufacturing capacity, the amount of spent fuel generated by nuclear power plants, the amount of separated plutonium and the use of other issues have been analyzed. The assumption that Fusion-Fission Hybrid Reactor fuel cycle system into our fuel cycle in2040, the analysis of the impact on demand of natural uranium and Pu separation of the cumulative amount of size. The cumulated amount of Pu and mathod of using the Pu were discussed.Physical characteristics of the fusion-fission hybrid reactor PWR combined cycle system was performed, and the research results is important for the sustainable development of China nuclear energy.更多还原