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.

为了获得聚变反应堆结构材料发展的基础数据，对Fe-Cr-Mn奥氏体钢、改性316不锈钢、铁素体钢和钒合金进行了中子、电子和/或离子辐照，并建立了模型合金。对这些合金也进行了辐照处理，得到以下结果和建议：（1）改进。 316不锈钢表现出较低的膨胀，并且预计这些钢在30dpa的较低剂量下具有较低的放射性激活，因此，改性316不锈钢可以用作较短时间的聚变反应材料。(2)相稳定性。低活性Fe-Cr-Mn钢在500℃以上时活性较低。因此，该类钢用于聚变反应堆时，可采用(3) ITER后DEMO将采用低活性Fe-(9-12)Cr基铁素体钢代替奥氏体钢，但仍存在一些问题。有一些问题需要解决，即由于嬗变而引入氦而导致脆化。(4)未来聚变反应堆材料预计将采用钒合金，因为其性能良好。该合金的放射性、抗辐照性和高温强度的特点目前可以推荐使用V-4Cr-Ti基合金，但这些合金对间隙杂质如氧和氢非常敏感。，如果将合金用作第一壁材料，应避免杂质的影响。（5）随着合金的长期发展，其他新材料如SiC和金属间化合物将被采用。需要。