本文關(guān)鍵詞： ODS鐵素體鋼 高能重離子 輻照損傷 延伸率 斷裂韌性　出處：《原子核物理評(píng)論》2015年03期 　論文類型：期刊論文

【摘要】：與傳統(tǒng)的鐵素體鋼相比,氧化物彌散強(qiáng)化(ODS)的鐵素體鋼具有更優(yōu)的耐高溫和抗輻照性能,近年來成為先進(jìn)核能裝置重要的候選結(jié)構(gòu)材料。在HIRFL的扇聚焦型回旋加速器(SFC)材料輻照終端,對(duì)一種氧化物彌散強(qiáng)化(ODS)鐵素體鋼MA956進(jìn)行了高能Ne離子輻照實(shí)驗(yàn),旨在研究級(jí)聯(lián)碰撞損傷和惰性氣體原子注入條件下該材料力學(xué)性能的變化。利用輻照終端的能量衰減裝置將SFC出口123.4 Me V的離子能量分解為介于38.5～121.0 Me V之間的30個(gè)入射能量值,并通過雙面輻照在厚度60μm的樣品中均勻產(chǎn)生了損傷。輻照劑量為9×1016ions/cm2,在樣品中的平均位移損傷為0.7 dpa,注入的Ne原子濃度為350 appm。輻照期間樣品溫度保持在440℃附近。對(duì)輻照前后的樣品分別在室溫和500℃下進(jìn)行了小沖桿試驗(yàn)(Small-punch Test),獲得了輻照前后樣品的加載位移曲線,由此得到該輻照條件下樣品的延性損失為18%～26%。通過掃描電子顯微鏡觀察了斷口形貌和厚度變化,估算了樣品的等效斷裂應(yīng)變和斷裂韌性。結(jié)果表明,MA956鋼經(jīng)過高能Ne離子輻照后等延伸率減小,斷裂韌性降低,樣品發(fā)生了一定的脆化。透射電鏡結(jié)果說明氧化物彌散相界面處微空洞的形成可能是導(dǎo)致脆化的原因。
[Abstract]:Compared with the traditional ferrite steel, the oxide dispersion strengthened ferrite steel has better high temperature resistance and radiation resistance. In recent years, it has become an important candidate for structural materials for advanced nuclear power plants. In HIRFL, SFC-based material irradiation terminals are used in the fan focusing cyclotron. A kind of oxide dispersion strengthened ferrite steel (MA956) was irradiated by high energy ne ion. In order to study the change of mechanical properties of the material under the condition of cascade collision damage and inert gas atom implantation, the SFC outlet 123.4 me was obtained by using the energy attenuating device of the irradiation terminal. The ion energy of V is decomposed into 30 incident energy values between 38.5 and 121.0 MeV. The average displacement damage in 60 渭 m samples was 0.7 dpa with a dose of 9 脳 10 ~ (16) ionos / cm ~ (2). The implanted ne atom concentration was 350 appm. The temperature of the samples remained around 440 鈩，

本文編號(hào)：1479031