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Influence of Neutron Irradiation on Hardening and Embrittlement Phenomena in Reactor Pressure Vessel Cladding Material

机译:中子辐射对反应堆压力容器包层材料中硬化和脆化现象的影响

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SA508 cl.3 reactor pressure vessel steel plates were overlay cladded with type ER309L welding consumables by submerged arc welding. The microstructure of the clad was composed of fcc austenite, a few percent of bcc δ-ferrite and brittle σ phase. The irradiation-induced hardening and its related mechanical property changes of the clad were investigated using tensile, small punch (SP) and electrical resistivity measurements. Neutron fluences of irradiated specimens at 290°C were ranged from ~5x10~(18) to ~5 x 10~(19) n/cm~2 (>1MeV). Not only yield stress but electrical resistivity were increased with irradiation and the δ-ferrite showed an approximately 1.5 times higher hardening than the austenite matrix. The general hardening may come from the irradiation-produced fine size defect clusters in the austenite matrix. The SP ductile/brittle transition temperature (SP-DBTT) moved to higher temperature with irradiation, and the SP-DBTT was substantially influenced by the amount of brittle σ phase.
机译:SA508 CL.3反应器压力容器钢板通过浸没电弧焊接覆盖使用ER309L焊接型型ER309L焊接耗材。包层的微观结构由FCC奥氏体组成,少量的BCCδ-铁氧体和脆性σ相。使用拉伸,小冲头(SP)和电阻率测量来研究辐照诱导的硬化及其相关的机械性能变化。 290℃下照射标本的中子流量为〜5x10〜(18)至〜5×10〜(19)n / cm〜2(> 1mev)。不仅屈服应力但电阻率随着辐射而增加,并且δ-铁素体显示比奥氏体基质高约1.5倍。一般硬化可以来自奥氏体基质中的照射产生的细尺寸缺陷簇。 SP球墨/脆化转变温度(SP-DBTT)移动到较高温度的辐照,SP-DBTT基本上受脆性σ相的影响。

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