首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Comparison of nuclear irradiation parameters of fusion breeder materials in high flux fission test reactors and a fusion power demonstration reactor
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Comparison of nuclear irradiation parameters of fusion breeder materials in high flux fission test reactors and a fusion power demonstration reactor

机译:高通量裂变试验反应堆和核聚变示范反应堆中核种材料的核辐射参数比较

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摘要

Nuclear irradiation parameters relevant to displacement damage and burn-up of the breeder materials Li2O, Li4SiO4 and Li2TiO3 have been evaluated and compared for a fusion power demonstration reactor and the high flux fission test reactor (HFR), Petten, the advanced test reactor (ATR, INEL) and the Japanese material test reactor (JMTR, JAERI). Based on detailed nuclear reactor calculations with the MCNP Monte Carlo code and binary collision approximation (BCA) computer simulations of the displacement damage in the polyatomic lattices with MARLOWE, it has been investigated how well the considered HFRs can meet the requirements for a fusion power reactor relevant irradiation. It is shown that a breeder material irradiation in these fission test reactors is well suited in this regard when the neutron spectrum is well tailored and the Li-6-enrichment is properly chosen. Requirements for the relevant nuclear irradiation parameters such as the displacement damage accumulation, the lithium burn-up and the damage production function W(T) can be met when taking into account these prerequisites. Irradiation times in the order of 2-3 full power years are necessary for the HFR to achieve the peak values of the considered fusion power Demo reactor blanket with regard to the burn-up and, at the same time, the dpa accumulation. (C) 2000 Elsevier Science B.V. All rights reserved. [References: 13]
机译:对于聚变动力演示反应堆和高通量裂变试验反应堆(HFR),佩滕,高级试验反应堆(ATR),已经评估并比较了与核种材料Li2O,Li4SiO4和Li2TiO3的位移损伤和燃尽有关的核辐射参数。 ,INEL)和日本材料测试反应堆(JMTR,JAERI)。基于使用MCNP蒙特卡罗代码进行的详细核反应堆计算以及使用MARLOWE进行的多原子晶格位移损失的计算机模拟二进制碰撞逼近(BCA)计算机模拟,研究了考虑的HFR如何满足聚变动力堆的要求相关辐射。结果表明,在适当调整中子谱并适当选择Li-6富集的情况下,这些裂变测试反应堆中的种核物质辐射非常适合此方面。当考虑到这些前提条件时,就可以满足相关核辐射参数的要求,例如位移损伤累积,锂燃烧和损伤产生函数W(T)。对于HFR,要达到燃尽以及同时dpa积累方面考虑的聚变动力演示反应堆毯子的峰值,需要2-3全功率年的辐照时间。 (C)2000 Elsevier Science B.V.保留所有权利。 [参考:13]

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