首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Prediction of J-R curves and thermoelectric power evolution of cast austenitic stainless steels after very long-term aging (200,000 h) at temperatures below 350 degrees C
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Prediction of J-R curves and thermoelectric power evolution of cast austenitic stainless steels after very long-term aging (200,000 h) at temperatures below 350 degrees C

机译:在低于350℃的温度下非常长期老化(200,000h)后铸造奥氏体不锈钢的J-R曲线和热电动力演化的预测

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Cast austenitic stainless steels (CASS) are materials used to fabricate many important safety-related components in the primary circuits of light water reactors since the early 1970's. The primary circuit, which transports heated water by nuclear reaction to steam generators, is subjected to in-service temperatures between 285 degrees C and 325 degrees C. Under these conditions, CASS undergo thermal aging which may significantly affect their mechanical properties and more especially their fracture toughness. From a metallurgical point of view, the changes in mechanical properties are attributable to several solid-state phase transformation processes including the spinodal decomposition of the ferritic phase and the precipitation of G phase. The kinetics of these phase transformations depends primarily on the time and temperature of aging, secondly on the chemical composition of the heat (chromium, molybdenum, silicon and nickel contents) and thirdly on the heat treatments performed during component manufacturing. The prediction of the long-term behavior of CASS is an important industrial issue for nuclear power plant operators. In the early 1980's, Electricite De France (EDF) engaged an unparalleled laboratory aging program that is still in progress. Presently, some materials have been aged for more than 200,000 hat low temperatures. The results of this program allow the development of prediction models for Charpy-impact energies, J - R curves and thermoelectric power values much more precise than those proposed so far, based on aging at 400 degrees C and rarely exceeding 30,000 h. These prediction models are described in this paper. (C) 2020 Elsevier B.V. All rights reserved.
机译:铸造奥氏体不锈钢(CASS)是自20世纪70年代初以来,用于在轻水反应器的主要电路中制造许多重要的安全相关组件。通过核反应将加热水传送到蒸汽发生器的初级回路在这些条件下在285℃和325摄氏度之间进行在使用的温度下,CASS经历热老化,这可能会显着影响其机械性能,更尤其是其断裂韧性。从冶金的角度来看,机械性能的变化可归因于几种固态相变过程,包括铁素体相的旋膜分解和G相的沉淀。这些相变的动力学主要取决于老化的时间和温度,其次在热(铬,钼,硅和镍含量)的化学成分上,第三,在组分制造期间进行的热处理。对CASS长期行为的预测是核电厂运营商的重要产业问题。在20世纪80年代初,France(EDF)的电力德国(EDF)从事一项无与伦比的实验室老龄化计划,仍在进行中。目前,一些材料已经老化为200,000多颗帽子低温。该计划的结果允许开发用于夏比冲击能量,J - R曲线和热电功率值的预测模型比到目前为止所提出的那些,基于400摄氏度的老化,并且很少超过30,000小时。本文描述了这些预测模型。 (c)2020 Elsevier B.v.保留所有权利。

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