论文部分内容阅读
一、开展快堆包壳材料轻离子辐照工作的意义快堆堆芯材料(包括包壳材料和组件材料广泛采用316不锈钢)处在高的工作温度(>500℃)及高注量快中子(E>0.1 MeV)的辐照场下工作。在整个寿期内,要经受注量达3×10~(23)n/cm~2的快中子辐照,相当于100~120 dpa。在超过空洞孕育期(~10~(22)n/cm~2)后,包壳材料出现严重的辐照肿胀(对316不锈钢,在快堆寿期末,肿胀量可达到10%),其肿胀按(φt)~n方式增加,其中φ为快中子注量,t为时间,n为大于1的指数。对快堆
First, the significance of the work to carry out fast ionizing cladding material light ion irradiation Fast reactor core material (including the cladding material and component materials widely used 316 stainless steel) at high working temperature (> 500 ℃) and high-speed injection (E> 0.1 MeV) under the irradiation field. Throughout the life, to withstand the fluence of 3 × 10 ~ (23) n / cm ~ 2 fast neutron irradiation, equivalent to 100 ~ 120 dpa. After exceeding the cavity incubation period (~ 10 ~ (22) n / cm ~ 2), the cladding material developed severe radiation swelling (up to 10% for 316 stainless steel at the end of fast reactor life) and swelling Increases by (φt) ~ n, where φ is the fast neutron fluence, t is the time, and n is an exponent that is greater than one. Fast reactor