Neutronic analysis of Z-pinch driven fusion-fission hybrid reactor blanket
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摘要: 作为一种有竞争力的能源系统，Z箍缩聚变裂变混合堆（Z-FFR）正在开展概念研究，包层研究正是其中重要的一部分。建立了Z-FFR包层设计模型，分析了包层影响因素、中子平衡、通量与功率密度、燃耗等方面，表明该包层设计在50年内能量放大因子、氚增殖比和燃料增殖比的平均值分别为14.91, 1.294和5.140，满足设计要求。针对聚变源的脉冲特性进行了包层的瞬态中子学分析，发现燃料区中子脉冲可分为聚变中子、瞬发裂变中子和缓发裂变中子脉冲三个部分，绝大部分热量约在0.01 s内沉积。结果较完整地给出了Z-FFR包层的中子学参数，为概念研究提供了基础。
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关键词:
- Z箍缩聚变裂变混合堆 /
- 包层 /
- 中子学 /
- 瞬态
Abstract: As a competitive energy system, Z-pinch driven fusion-fission hybrid reactor (Z-FFR) is developed in concept study stage, while blanket research is one important part. In this paper the Z-FFR blanket design model is set up, and influence factor, neutron balance, flux, power density and burnup of the model are analyzed. The average energy multiplication factor (M), tritium breeding ratio (TBR) and fuel breeding ratio (F/B) for 50 years are 14.91, 1.294 and 5.140, respectively, which can meet the design requirements. Considering pulse characteristic of fusion source, the transient neutronics properties are also studied. In fuel zone neutron, there are three parts of pulse: fusion neutron pulse, prompt fission neutron pulse and delayed fission neutron pulse. Most of the energy in fuel zone is deposited in 0.01 s. The complete neutron parameters of Z-FFR blanket are given, which provide the foundation for the concept study.-
Key words:
- Z-pinch driven fusion-fission hybrid reactor /
- blanket /
- neutronics /
- transient
期刊类型引用(3)
1. 丁文杰，郭海兵，黄洪文，郭斯茂. 湍流模型对瞬态流固耦合换热数值模拟影响分析. 原子能科学技术. 2019(02): 304-311 . 
百度学术2. Yong-Gang Mo，Zhi-Lin Chen，Hong-Hu Song，Yang Yang，Jing Wu，Dong Zhang. Preliminary analysis of tritium fuel cycle in Z-pinch-driven fusion–fission hybrid reactor. Nuclear Science and Techniques. 2018(07): 118-123 . 必应学术3. 丁文杰，郭海兵，王少华，黄洪文. 高功率脉冲加热条件下燃料模块流动传热特性研究. 原子能科学技术. 2017(12): 2118-2124 . 百度学术其他类型引用(2)
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