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Optimization of Tritium Breeding and Shielding Analysis to Plasma in ITER Fusion Reactor

机译:近料融合反应堆血浆氚育种和屏蔽分析的优化

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The development of fusion energy is one of the important International energy strategies with the important milestone is ITER (International Thermonuclear Experimental Reactor) project, initiated by many countries, such as: America, Europe, and Japan who agreed to set up TOKAMAK type fusion reactor in France. In ideal fusion reactor the fuel is purely deuterium, but it need higher temperature of reactor. In ITER project the fuels are deuterium and tritium which need lower temperature of the reactor. In this study tritium for fusion reactor can be produced by using reaction of lithium with neutron in the blanket region. With the tritium breeding blanket which react between Li-6 in the blanket with neutron resulted from the plasma region. In this research the material used in each layer surrounding the plasma in the reactor is optimized. Moreover, achieving self-sufficiency condition in the reactor in order tritium has enough availability to be consumed for a long time. In order to optimize Tritium Breeding Ratio (TBR) value in the fusion reactor, there are several strategies considered here. The first requirement is making variation in Li-6 enrichment to be 60%, 70%, and 90%. But, the result of that condition can not reach TBR value better than with no enrichment. Because there is reduction of Li-7 percent when increasing Li-6 percent. The other way is converting neutron multiplier material with Pb. From this, we get TBR value better with the Be as neutron multiplier. Beside of TBR value, fusion reactor can analyze the distribution of neutron flux and dose rate of neutron to know the change of neutron concentration for each layer in reactor. From the simulation in this study, 97% neutron concentration can be absorbed by material in reactor, so it is good enough. In addition, it is required to analyze spectrum neutron energy in many layers in the fusion reactor such as in blanket, coolant, and divertor. Actually material in that layer can resist in high temperature and high pressure condition for more than ten years.
机译:融合能源的发展是重要的国际能源策略之一,重要的里程碑是迭代(国际热核实验反应堆)项目,由许多国家发起,例如:美国,欧洲和日本同意设定托卡马克式融合反应堆在法国。在理想的融合反应器中,燃料纯粹是氘,但它需要更高的反应器温度。在ITER项目中,燃料是氘和氚,需要较低的反应器温度。在该研究中,可以通过使用橡皮布区域中的中子的反应来制备用于融合反应器的氚。与氚繁殖毯,在橡皮布中的Li-6之间反应,中子从等离子体区域产生。在本研究中,优化了反应器中等离子体周围的每层中使用的材料。此外,在订单氚中实现反应器中的自给自足条件有足够的可用性来消耗很长时间。为了优化融合反应堆中的氚育种比(TBR)值,这里考虑了几种策略。第一个要求是将Li-6富集的变化为60%,70%和90%。但是,这种情况的结果比没有富集更好地达到TBR值。因为当增加Li-6%时,Li-7%降低了Li-7%。另一种方式是用Pb转换中子倍增器材料。由此,我们使用中子倍增器更好地获得TBR值。除了TBR值之外,熔融反应器可以分析中子通量的分布和中子剂量的分布,以了解反应器中每层中子浓度的变化。从本研究中的仿真来看,97%中子浓度可以通过反应器中的材料吸收,因此足够好。另外,需要分析融合反应器中的许多层中的谱中子能量,例如橡皮布,冷却剂和倒档器。实际上,该层的材料可以在高温和高压条件下抵抗十多年。

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