Nuclear and Thermal Analyses of Supercritical-water-cooled Solid Breeder Blanket for Fusion DEMO Reactor
Nuclear and Thermal Analyses of Supercritical-water-cooled Solid Breeder Blanket for Fusion DEMO Reactor
复制标题
聚变DEMO反应堆超临界水冷固体增殖毯的核分析和热分析
DOI：
10.1080/18811248.2001.9715131
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发表时间：
2001
影响因子：
1.2
通讯作者：
Y. Ohara
中科院分区：
文献类型：
--
作者：
Y. Yanagi;S. Sato;M. Enoeda;T. Hatano;S. Kikuchi;T. Kuroda;Y. Kosaku;Y. Ohara
在聚变示范堆的设计研究中，为了获得较高的热效率，采用超临界水作为固体增殖包层的冷却剂。包层由固体增殖鹅卵石(Li2O)和中子倍增鹅卵石(Be)组成，它们由冷却板径向分开。第一壁和孕育区分别在伪临界温度以下和以上被超临界水冷却。用一维核热计算估算了温度分布和氚增殖率(TBR)。在中子壁负荷为5 mW/m~2、~6Li丰度为30%、增殖区进口冷却液温度为380℃的条件下，通过优化增殖区温度分布，获得了高达1.47的局部TBR。在增殖区冷却温度较高的情况下，局部TBR降至1.40。这意味着，超临界水冷包层的净总热效率有望高于1.0，其增殖区的温度分布将通过跟随冷却剂温度进行优化，其中增殖区的覆盖率假设为70%。
Within a design study of a fusion DEMO reactor aiming at demonstrating technologies of fusion power plant, supercritical water is applied as a coolant of solid breeder blanket to attain high thermal efficiency. The blanket has multi-layer composed of solid breeder pebbles (Li2O) and neutron multiplier pebbles (Be) which are radially separated by cooling panels. The first wall and the breeding region are cooled by supercritical water below and above the pseudo- critical temperature, respectively. Temperature distribution and tritium breeding ratio (TBR) have been estimated by one-dimensional nuclear and thermal calculations. The local TBR as high as 1.47 has been obtained after optimization of temperature distribution in the breeder region under the following conditions: neutron wall loading of 5 MW/m2, 6Li enrichment of 30% and coolant temperature at inlet of breeder region of 380°C. In the case of the higher coolant temperature 430°C of the breeder region the local TBR was reduced to be 1.40. This means that the net TBR higher than 1.0 could be expected with the supercritical-water-cooled blanket, whose temperature distribution in the breeder region would be optimized by following the coolant temperature, and where a coverage of the breeder region is assumed to be 70%.