目前，核能的利用都是由重核裂变产生，且存在核安全、核燃料利用率低以及核废料难处理等方面的挑战。受控核聚变能被认为是最理想的能源形式，但由于其对等离子体约束的条件苛刻，至今尚未实现。聚变-裂变混合堆作为外中子源驱动的次临界装置，不存在临界堆的核安全问题，同样它的燃料利用率高，且能够嬗变长寿命锕系核素。聚变-裂变混合堆对托卡马克装置的要求比聚变堆低一个数量级，目前的托卡马克装置就能实现。要实现聚变-裂变混合堆的工程化，首先需要进行包层概念设计的物理分析。本文使用清华大学核能与新能源技术研究院研制开发的MCNP-ORIGEN耦合程序COUPLE2.0程序对混合堆包层进行燃耗计算。包层模型为“D”型板状结构。通过对包层中不同冷却剂、裂变燃料和氚增殖剂等进行比较，最终选取以轻水作为冷却剂、铀锆合金作为裂变燃料、原硅酸锂作为氚增殖剂的包层结构。包层水铀比约等于2.0，这种结构的包层既有较高的快中子通量，又有高的热中子通量，属于快热耦合形式的包层。在满足氚增殖比大于1.0的要求下，它具有较高的Keff和能量放大倍数，从而降低了对聚变装置的要求，且燃料增殖性能好。混合堆初装料使用天然铀富集度的铀锆合金，初装料所用天然金属铀是相同功率压水堆的1.57倍。能够设计比压水堆更长的换料周期，本文设计5年一次换料的循环周期，进行12炉换料，共60年。考虑到锕系核素的嬗变，将其放入第一燃料区中，计算结果表明，包层中易裂变核素总量和长寿命锕系核素总量均能达到一个稳定的状态。长寿命锕系核素的生成量是相同功率压水堆的42%，60年内，75.2%的裂变能是由燃料增殖生成的钚-239和钚-241裂变产生。混合堆比功率仅为压水堆的15%，对热工水力设计有利。为了实现聚变-裂变混合堆的早日使用，需要研究压水堆和聚变-裂变混合堆共生体系的建立。本文提出多种方案。包括混合堆使用压水堆燃料生产中产生的贫铀作为燃料，以及压水堆乏燃料作为燃料等。

Nowadays, only fission energy is used, but it is being challenged by the nuclear safety problem, the low efficiency of nuclear fuel and the desposal of nuclear waste. Controlled fusion energy is considerd as the ideal energy, but as it requires high parameter plasma, it has not been realized yet.Fusion-Fission Hybrid Reactor (FFHR), being a subcritical system driven by external fussion neutron, doesn’t have nuclear criticality safety problem, could utilize the nuclear fuel more efficiently, and could perform Long Life Minor Actinides (LLMA) transmucation. Its requirement on plasma is lower than the fusion reactor for electric generation, and the tokamak nowadays can achieve the goal. To realize the FFHR potential engineering, the conceptual physical degisn of a blanket must be first.This thesis uses COUPLE2.0, which is a coupling code of MCNP and ORIGEN and has been developed by Institute of Nuclear and New Energy Technology, Tsinghua University, to calculate burnup of FFHR blanket. The blanket is designed as “D” shaped model with plate fuels.By comparing the different kinds of coolant, fission fuel and tritium breeding material etc, finally this thesis selects the light water as coolant, the U-Zr alloy as fuel and Li4SiO4 as tritium breeding material. The volume ratio of water and fuel is approximately 2.0. This kind of blanket has fast-thermal spectrum because the fast flux and the thermal flux are of both high peaks. Under the precondition that tritium breeding ratio (TBR) must be larger than 1.0, the Keff and energy multiplication of the blanket are both comparatively high, and so they make the technical requirements of fussion facility much lower, and the fuel breeding ratio of this blanket is also good.The first fuel loading of the blanket is U-Zr alloy (the atom concentration of 235U is the same as nature Uranium, i.e. 0.71%). The total mass of nature uranium used in initial core is 1.57 times as used by initial Pressure Water Reactor (PWR) with the same power. It can be designed with longer refueling cycle. This thesis designs 5 years to be a refueling cycle with totally 12 cycles (60 years). Considing the transmutation of LLMA, MA is put in the first fuel plate. The result shows that the total mass of fissile nuclides and LLMA could reach balance when the burnup is deep enough. The total mass of LLMA generated in 60 years is about 42% of PWR with the same power. 75.2% fission power of the blanket is generated by Pu-239 and Pu-241. The blanket’s specific power is only 15% of PWR. This is good for the thermal hydraulic design of FFHR.In order to realize early application of FFHR, we must study the commensal system of PWR and FFHR. This paper has bring forward several plans about this such as FFHR uses the depleted uramium, which is generated when condensing the uranium for PWR, as the fuel or uses the waste of PWR as fuel etc.