國產(chǎn)RPV鋼輻照脆化行為的正電子湮滅研究

國產(chǎn)RPV鋼輻照脆化行為的正電子湮滅研究Positron Annihilation Investigation of Embrittlement Behavior in Chinese RPV Steels after Irradiation

反應(yīng)堆壓力容器（Reactor Pressure Vessel, RPV）作為核電站的關(guān)鍵部件之一，壽期內(nèi)很難更換，從而決定了反應(yīng)堆的壽命。高溫氣冷堆具有良好的固有安全性，是第四代先進(jìn)核能系統(tǒng)的首選堆型之一。然而，因?yàn)樗c壓水堆具有不同的服役溫度（壓水堆290 oC，高溫堆250 oC），所以關(guān)于服役于高溫氣冷堆RPV鋼的輻照脆化行為仍有待研究。本文選取了我國高溫氣冷堆的RPV鋼A508-3 和純Fe進(jìn)行實(shí)驗(yàn)，采用3 MeV鐵離子進(jìn)行高溫（250 oC）與常溫輻照，損傷分別達(dá)0.1 dpa、0.5 dpa、1.0 dpa，對樣品分別進(jìn)行正電子湮滅和納米壓痕硬度（表征脆化行為）研究。結(jié)果表明，輻照會(huì)使材料內(nèi)部產(chǎn)生缺陷，這種缺陷以空位型缺陷和溶質(zhì)原子團(tuán)簇缺陷為主。且高溫輻照產(chǎn)生的缺陷密度低于常溫輻照，其中高溫的退火效應(yīng)使材料內(nèi)部缺陷發(fā)生一定程度的回復(fù)。同時(shí)，輻照后RPV鋼和純Fe都產(chǎn)生了一定程度的硬化，硬化程度隨輻照劑量的增加而增強(qiáng)。對于RPV鋼，高溫輻照比常溫輻照使材料內(nèi)部產(chǎn)生更少的空位型缺陷，更多的溶質(zhì)原子團(tuán)簇型缺陷。

The reactor pressure vessel (RPV) is the key component in the nuclear power plant, which is considered irreplaceable and can be the life-limiting feature of the operation of nuclear power plant if its mechanical properties degrade sufficiently. High Temperature Gas Cooled Reactor (HTGR) has perfect inherent safety, which is intended to be one of the fourth generation advanced nuclear reactor. However, HTGR has different service temperature with pressurized water reactor (PWR), that HTGR is 250 oC and PWR is 290 oC. So the irradiation behaviour of RPV in HTGR is expecting to be investigated. In this paper, 3 MeV Fe-ion irradiation was performed on a Chinese A508-3 reactor pressure vessel steel -for high-temperature gas-cooled reactors and pure Fe under room temperature and high temperature (250 oC). The ion doses were 0.1 dpa, 0.5 dpa and 1.0 dpa for both room temperature irradiation and high temperature irradiation. Positron annihilation Doppler broadening spectroscopy experiments and nano-indentation tests (to perform embrittlement behavior) were conducted for characterization. It is found that after both room temperature irradiation and high temperature irradiation, the density of defects in the reactor pressure vessel steel and pure Fe increases, and the type of defects could be vacancy-type and solute cluster type. The defect density under high temperature irradiation is lower than that under room temperature irradiation. That is because high temperature can recover the defects formed during irradiation. The hardness test results show that for both the reactor pressure vessel steel and pure Fe, the irradiation hardening increases with increasing dose. Compared to room temperature irradiation, high temperature irradiation can produce more solute clusters and less vacancy-type defects in the reactor pressure vessel steel. So the irradiation hardening of the reactor pressure vessel steel might be caused mainly by the formation of solute clusters.

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