首页> 外文会议>International Conference on Structural Mechanics in Reactor Technology >IMPROVEMENT OF RADIATION EMBRITTLEMENT DEPENDENCES FOR WER-1000 PRESSURE VESSEL MATERIALS ON SERVICE-LIFE EXTENSION
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IMPROVEMENT OF RADIATION EMBRITTLEMENT DEPENDENCES FOR WER-1000 PRESSURE VESSEL MATERIALS ON SERVICE-LIFE EXTENSION

机译:延长使用寿命的WET-1000压力容器材料的辐射结垢程度的改善

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The results received by now while investigating the sets of surveillance specimens for WER-1000 reactor pressure vessels (RPV) are the most representative for studying and evaluation of radiation embrittlement of materials of this type of RPVs. It is primarily due to the fact that neutron irradiation of surveillance specimens (SS) of WER-1000 RPV materials is carried out with a flux density corresponding to the inner surface of a reactor pressure vessel opposite to the core with the average lead factor for sets of surveillance specimens intended for evaluation of radiation embrittlement varying from 0.5 to 3. On the base of SS research results, standard dependences have been developed and are currently in use for radiation embrittlement of WER-1000 RPV materials with the operation range limited by the value of fast neutron fluence of 6.4 × 10~(23) neutron/m~2 with the energy above 0.5 MeV where the general transition temperature is modelled as a sum of radiation and thermal contributions and the thermal component has a form of a function with the maximum which is hypothetically caused by carbide precipitation and coagulation [1,2]. Microstructure investigations of SS materials performed at the National Research Centre "Kurchatov Institute" after different time exposures failed to prove the hypothesis of carbide hardening under temperature aging and. at the same time, unambiguously showed the existence of significant radiation-and temperature-stimulated phosphoms segregation on grain boundaries and in interphase areas [3-5]. Thereby, there arose a necessity to develop a dependence that would account for the physical processes proceeding in the material under irradiation at the reactor operation temperature. Forecasting of the RPV material condition on service life extension up to 60 years and more requires an expansion of the validity range of the developed dependences to the maximum fast neutron fluence of - 8.0×10~(23) neutron/m~2. With this aim in view, the SS material was subjected to accelerated irradiation to gain higher fast neutron fluences and conservatism of the suggested dependences was verified on their extrapolation. On using the accelerated irradiation results for verification of the forecast conservatism for the developed dependences, account was taken of the effects related to the difference in time and rate of accelerated irradiation as compared to the conditions of RPV wall irradiation.
机译:目前,在调查WER-1000反应堆压力容器(RPV)的监视标本集时所获得的结果,对于研究和评估这类RPV的材料的辐射脆化最具代表性。这主要是由于以下事实:对WER-1000 RPV材料的监视标本(SS)进行中子辐照,其通量密度对应于与堆芯相对的反应堆压力容器的内表面,且每套的平均铅系数用于评估放射脆性的监视标本的范围从0.5到3。根据SS研究的结果,已经开发出标准依赖性,并且目前用于WER-1000 RPV材料的放射脆性,其操作范围受该值限制能量大于0.5 MeV的6.4×10〜(23)中子/ m〜2的快速中子通量的通量,其中一般转变温度以辐射和热贡献之和为模型,而热分量具有以下形式的函数形式:推测这是由碳化物的沉淀和凝结引起的[1,2]。在不同的时间暴露后,在国家研究中心“库尔恰托夫研究所”进行的SS材料的微观结构研究未能证明在高温时效时碳化物硬化的假说。同时,清楚地表明在晶界和相间区域存在显着的辐射和温度刺激的磷偏析[3-5]。因此,有必要发展一种依赖性,该依赖性将解释在反应器操作温度下在辐照下材料中进行的物理过程。预测RPV物质寿命延长60年以上的条件需要将已开发的依赖项的有效范围扩展到最大快中子注量-8.0×10〜(23)neutron / m〜2。出于这个目的,对SS材料进行加速辐照以获得更高的快速中子注量,并在其推断上证实了所建议依赖的保守性。在使用加速辐照结果验证已发展依赖性的预测保守性时,考虑了与RPV墙辐照条件相比,加速辐照时间和速率差异的相关影响。

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