在托卡马克实验装置中,D-T聚变反应释放出的14 Me V高能中子,与周围部件接触会引起包层材料活化、热负载过高等一系列问题,因此在包层设计和优化过程中,相关的中子学计算显得尤为重要。为了研究不同描述的中子源模型对中国聚变工程实验...在托卡马克实验装置中,D-T聚变反应释放出的14 Me V高能中子,与周围部件接触会引起包层材料活化、热负载过高等一系列问题,因此在包层设计和优化过程中,相关的中子学计算显得尤为重要。为了研究不同描述的中子源模型对中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)中子学计算的影响,使用基于蒙特卡罗方法的MCNP(Monte Carlo N Particle Transport Code)程序来模拟中子输运过程,分别计算点源、均匀体源、基于L、H、A模约束的中子源模型对不同中子学计算的影响。结果表明,不同描述的中子源模型对氚增殖比影响较小,对中子壁负载和功率密度分布影响比较明显。展开更多
聚变堆固态包层框架下,针对初步设计的聚变堆氦冷固态包层进行了中子学分析。选择增殖区的氚增殖剂和中子倍增剂分层分布方案,建立了20°对称D型轮胎环全堆计算模型,对聚变中子源分布离散化处理。借助M on te-C arlo粒子输运程序M ...聚变堆固态包层框架下,针对初步设计的聚变堆氦冷固态包层进行了中子学分析。选择增殖区的氚增殖剂和中子倍增剂分层分布方案,建立了20°对称D型轮胎环全堆计算模型,对聚变中子源分布离散化处理。借助M on te-C arlo粒子输运程序M CNP对聚变堆包层的氚增殖性能和核热功率进行了计算。结果表明,堆总体氚增殖率达到1.247,核热密度峰值在赤道包层模块,能够实现聚变堆运行的氚自持条件。展开更多
For the preparation of tritium fuel as the main and rare fuel of reactors in the fusion reactors, the reactor blanket must be designed so that it provides enough tritium breeding ratio. The tritium breeding ratio, TBR...For the preparation of tritium fuel as the main and rare fuel of reactors in the fusion reactors, the reactor blanket must be designed so that it provides enough tritium breeding ratio. The tritium breeding ratio, TBR, in the blanket of reactors should be greater than one, (TBR > 1), by applying lithium blanket. The calculations for proposed parameters (td , fb , η and tp), indicate that the estimated tritium breeding ratio is greater than one. The calculated TBR = 1.04 satisfies the tritium provision condition.展开更多
When one wants to simply estimate tritium breeding ratio （TBR）, the TBR may be reduced from a ＂local＂ TBR for the breeding zones of a blanket module by multiplying the breeder coverage （= the surface area of effe...When one wants to simply estimate tritium breeding ratio （TBR）, the TBR may be reduced from a ＂local＂ TBR for the breeding zones of a blanket module by multiplying the breeder coverage （= the surface area of effective breeding region / the surface area of the first wall around plasma）. When blanket modules are arranged~ the gap between neighboring modules and the frames of the modules are regarded as nombreeding zones. On the other hand, neutrons scattered in the non-breeding zones can enter breeding zones, contributing to tritium production. This means that the estimation method mentioned above tends to underestimate TBR. In order to assess the scattering effect quantitatively, we carried out a three-dimensional Monte Carlo N-particle transport MCNP-5 calculation. It was found from the calculation that there is little decrease in TBR for gaps less than 4 cm when the blanket thickness is 70 cm. The result indicates that such a wide allowance of the gap will facilitate access of remote handling equipment for the replacement of blanket modules and improve access of diagnostics.展开更多
文摘在托卡马克实验装置中,D-T聚变反应释放出的14 Me V高能中子,与周围部件接触会引起包层材料活化、热负载过高等一系列问题,因此在包层设计和优化过程中,相关的中子学计算显得尤为重要。为了研究不同描述的中子源模型对中国聚变工程实验堆(China Fusion Engineering Test Reactor,CFETR)中子学计算的影响,使用基于蒙特卡罗方法的MCNP(Monte Carlo N Particle Transport Code)程序来模拟中子输运过程,分别计算点源、均匀体源、基于L、H、A模约束的中子源模型对不同中子学计算的影响。结果表明,不同描述的中子源模型对氚增殖比影响较小,对中子壁负载和功率密度分布影响比较明显。
文摘聚变堆固态包层框架下,针对初步设计的聚变堆氦冷固态包层进行了中子学分析。选择增殖区的氚增殖剂和中子倍增剂分层分布方案,建立了20°对称D型轮胎环全堆计算模型,对聚变中子源分布离散化处理。借助M on te-C arlo粒子输运程序M CNP对聚变堆包层的氚增殖性能和核热功率进行了计算。结果表明,堆总体氚增殖率达到1.247,核热密度峰值在赤道包层模块,能够实现聚变堆运行的氚自持条件。
文摘For the preparation of tritium fuel as the main and rare fuel of reactors in the fusion reactors, the reactor blanket must be designed so that it provides enough tritium breeding ratio. The tritium breeding ratio, TBR, in the blanket of reactors should be greater than one, (TBR > 1), by applying lithium blanket. The calculations for proposed parameters (td , fb , η and tp), indicate that the estimated tritium breeding ratio is greater than one. The calculated TBR = 1.04 satisfies the tritium provision condition.
文摘When one wants to simply estimate tritium breeding ratio （TBR）, the TBR may be reduced from a ＂local＂ TBR for the breeding zones of a blanket module by multiplying the breeder coverage （= the surface area of effective breeding region / the surface area of the first wall around plasma）. When blanket modules are arranged~ the gap between neighboring modules and the frames of the modules are regarded as nombreeding zones. On the other hand, neutrons scattered in the non-breeding zones can enter breeding zones, contributing to tritium production. This means that the estimation method mentioned above tends to underestimate TBR. In order to assess the scattering effect quantitatively, we carried out a three-dimensional Monte Carlo N-particle transport MCNP-5 calculation. It was found from the calculation that there is little decrease in TBR for gaps less than 4 cm when the blanket thickness is 70 cm. The result indicates that such a wide allowance of the gap will facilitate access of remote handling equipment for the replacement of blanket modules and improve access of diagnostics.
