CAJ | 학술논문

聚变-裂变混合能源堆包括聚变中子源和次临界能源堆，主要目标是生产电能。回顾了国内外混合堆的发展历史，给出混合能源堆设计的边界条件和约束条件，说明次临界能源堆以铀锆合金为燃料、水为冷却剂的设计思想。利用输运燃耗耦合程序 MCORGS 计算了混合能源的燃耗，给出了中子有效增殖因数、能量放大倍数和氚增殖比等物理量随时间的变化。通过分析能谱和重要核素随燃耗时间的变化，说明混合能源堆与核燃料增殖、核废料嬗变混合堆的不同特点。论述了混合堆的热工设计并进行了安全分析。对于燃耗数值模拟程序，通过多家对算，保证其计算结果的可信性。针对次临界能源堆的特点，利用贫铀球壳建立了贫铀聚乙烯装置和贫铀 LiH 装置，并且专门设计加工了天然铀装置，开展铀裂变率、造钚率、产氚率等中子学积分实验，验证了数值模拟的可靠性。
취변-렬변혼합능원퇴포괄취변중자원화차림계능원퇴，주요목표시생산전능。회고료국내외혼합퇴적발전역사，급출혼합능원퇴설계적변계조건화약속조건，설명차림계능원퇴이유고합금위연료、수위냉각제적설계사상。이용수운연모우합정서 MCORGS 계산료혼합능원적연모，급출료중자유효증식인수、능량방대배수화천증식비등물리량수시간적변화。통과분석능보화중요핵소수연모시간적변화，설명혼합능원퇴여핵연료증식、핵폐료선변혼합퇴적불동특점。논술료혼합퇴적열공설계병진행료안전분석。대우연모수치모의정서，통과다가대산，보증기계산결과적가신성。침대차림계능원퇴적특점，이용빈유구각건립료빈유취을희장치화빈유 LiH 장치，병차전문설계가공료천연유장치，개전유렬변솔、조비솔、산천솔등중자학적분실험，험증료수치모의적가고성。
In this paper,we propose a preliminary design for a fusion-fission hybrid energy reactor (FFHER),based on cur-rent fusion science and technology and well-developed fission technology.Design rules are listed and a primary concept blanket with uranium alloy as fuel and water as coolant is put forward.The uranium fuel can be natural uranium,LWR spent fuel,or de-pleted uranium.The FFHER design can increase the utilization rate of uranium in a comparatively simple way to sustain the de-velopment of nuclear energy.The interaction between the fusion neutron and the uranium fuel with the aim of achieving greater energy multiplication and tritium sustainability is studied.Other concept hybrid reactor designs are also reviewed.Integral neu-tron experiments were carried out to verify the credibility of our proposed physical design.The combination of the physical design with the related thermal hydraulic design,alloy fuel manufacture,and nuclear fuel cycle programs provides the science and tech-nology basis for future development of the FFHER concept in China.