Study of Low Activation Materials for Fusion Reactor

聚变反应堆低活化材料的研究

基本信息

批准号：
05044071
负责人：
TAKAHASHI Heishichiro
金额：
$ 3.84万
依托单位：
Hokkaido University
依托单位国家：
日本
项目类别：
Grant-in-Aid for international Scientific Research
财政年份：
1993
资助国家：
日本
起止时间：
1993 至 1995
项目状态：
已结题

项目摘要

In order to obtain the fundamental data on the development of fusion reactor structural materials, Fe-Cr-Mn austenitic steel, modified 316 Stainless steels, ferritic steels and vanadium alloys were irradiated by neutrons, electrons and/or ions irradiations. Furtheremore the model alloys related these alloys were also irradiated. From these experimentals facts the following results and suggetion were obtained :(1) The modified 316 stainless steel showed lower swelling, and it is expected that these steels are lower radio-activated at lower dose of 30dpa. Therefore, the modified 316 stainless steels could be used as fusion react-or marerials for shorter periods.(2) Phase stability of low activated Fe-Cr-Mn steels was lower at temperature of above 500ﾟC.Therefore, when this type of steels are used for fusion reactor, it is aveirable as buck-up materials of structure components at lower temperature below 200ﾟC.(3) Instead of austenitic steels, the low activated Fe-(9-12)Cr based ferritic steels will be available for DEMO after ITER.However, there is still psome problems to be resolved, that is embrittlement due to helium introduced as a result of transmutation.(4) Future materials for fusion reactor, vanadium alloys are expected, because of the well characteristics of this alloy for radio-activation, the resistance against irradiation and high temperature strength. At present the alloy of V-4Cr-Ti based alloys can be recommended, but these alloys are very sensitive for interstitial impurities such as oxygen and hydrogen. Therefore, if the alloys will be used as first wall materials, the effect of the impurities should be avoided.(5) As the alloy development for long periods, other new matreials such as SiC and intermetallic coumpound will be needed.

为了获得有关融合反应堆结构材料开发的基本数据，Fe-Cr-Mn奥氏体钢（修饰的316条不锈钢，铁素体钢和钒合金）被中子，电子和/或离子辐照照射。这些合金也被辐照了这些合金的模型合金。从这些实验事实中得出以下结果和建议：（1）修饰的316条不锈钢显示出较低的吞咽，预计这些钢在较低剂量的30dPa时会较低的放射激活。因此，经过修改的316台不锈钢可以用作较短时间的融合反应。（2）低活化的Fe-Cr-Mn钢的相位稳定性在温度下较低，高于500°C.，当这种类型的钢用于融合反应器时，它是可以在低于下部温度下的结构材料来促进的。 Fe-（9-12）基于CR的铁质钢将在ITER之后进行演示。但是，仍然存在PSOME问题，这是可以解决的，这是由于翻译而引入的氦气。（4）融合反应堆的未来材料，凡兰德合金的未来材料是可以预期的，因为这种合同的良好特征是对射电活动的良好特征，而耐药的强度，高高的温度和高度的高度高高，因此构成了Inradivation和Irnrady Irnradivation andradivation andradivation andradivation andradiviation andradiviation andradiviation。目前，可以建议使用基于V-4CR-TI的合金合金，但是这些合金对氧气和氢等间质杂质非常敏感。因此，如果合金将用作第一壁材料，则应避免杂质的作用。（5）作为长期合金发育，还需要其他新的临时材料，例如SIC和金属间质量。