首页> 外文会议>Symposium on effects of radiation on materials >COMPARISON OF BR3 SURVEILLANCE AND VESSEL PLATES TO THE SURROGATE PLATES REPRESENTATIVE OF THE YANKEE ROWE PWR VESSEL
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COMPARISON OF BR3 SURVEILLANCE AND VESSEL PLATES TO THE SURROGATE PLATES REPRESENTATIVE OF THE YANKEE ROWE PWR VESSEL

机译:BR3监测和船板对Yankee Rowe PWR船舶代理板代表代表的比较

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The sister pressure vessels at the BR3 and Yankee Rowe PWR plants were operated at lower-than-usual temperature (≈260°C) and their plates were austenitized at higher-than-usual temperature (≈ 970°C)- a heat treatment leading to a coarser microstructure than is typical for the fine grain plates considered in development of USNRC Regulatory Guide 1.99. The surveillance programs provided by Westinghouse for the two plants were limited to the same A302-B plate representative of the Rowe vessel upper shell plate; this material displayed outlier behavior characterized by a 41J. Charpy-V Notch shift significantly larger than predicted by Regulatory Guide 1.99. Because lower irradiation temperature and nickel alloying are generally considered detrimental to irradiation sensitivity, there was a major concern that the nickel-modified lower Rowe plate and the nickel-modified BR3 plate may become too embrittled to satisfy the toughness requirements embodied in the PTS screening criterion. This paper compares three complementary studies undertaken to clarify these uncertainties: 1) The accelerated irradiation and test program launched in 1990 by Yankee Atomic Electric Company using typical vessel plate materials containing 0.24% copper at two nickel levels: YA1, 0.63% (A533-B) and YA9, 0.19% (A302-B). These were heat-treated to produce the coarse and fine grain microstructures representative of the Yankee/BR3 and the Regulatory Guide plates, respectively; 2) The BR3 surveillance and vessel testing program: this vessel was wet-annealed in 1984, relicensed for operation till the plant shutdown in 1987, and was trepanned in early 1995; 3) The accelerated irradiations in the Belgian test reactor BR2 of the Yankee coarse grain plates YA1 and YA9 together with BR3 vessel specimens extracted at nozzle elevation, a location with negligible radiation exposure. It is contended that the PTS screening criterion was never attained by the BR3 and Rowe plates, and that the BR3 vessel anneal was neither necessary nor efficient. Furthermore, the practice to index fracture toughness to an absorbed energy level of 41 Joules in the CVN impact test is challenged in light of micromechanical modeling considerations and of supportive three-point slow bend precracked Charpy tests of the BR3 and YA1 plates. Finally, the sensitivity of embrittlement, annealing and post-anneal reembrittlement to irradiation temperature, nickel and other alloying or impurity elements is discussed, with a view to justify reducing the conservatism of regulatory prescriptions for these materials.
机译:BR3和Yankee Rowe PWR植物的姐妹压力容器在低于常见的温度(≈260℃),在高于通常的温度下(≈970℃) - 热处理导致它们的板材奥氏体对于在USNRC监管指南1.99开发中考虑的细粒印板的典型微观结构比典型的微观结构。两家工厂的西屋提供的监督计划仅限于COWE血管上壳板的相同A302-B板;此材料显示了41J特征的异常行为。 Charpy-V Notch换档比监管指南1.99的预测大致大。由于较低的照射温度和镍合金化通常被认为是有害的照射敏感性,因此主要担心镍改性的下排板和镍改性的BR3板可能太脆化,以满足PTS筛选标准中体现的韧性要求。本文比较了三项互补研究,以澄清这些不确定性:1)扬科原子电气公司于1990年推出的加速照射和试验方案,使用典型的血管板材,含有0.24%铜的镍水平:YA1,0.63%(A533-B )和Ya9,0.19%(A302-B)。热处理这些以产生代表Yankee / BR3和调节板的粗糙和细粒微结构; 2)BR3监控和船舶测试程序:该船舶于1984年湿润,转龙持续,直至1987年的工厂关闭,并于1995年初进行了培训; 3)Yankee粗粒板Ya1和Ya9的比利时测试反应器Br2的加速照射与喷嘴高度提取的BR3血管标本一起,辐射暴露的位置可忽略不计的位置。拟见的是,BR3和Rowe板从未获得PTS筛选标准,并且BR3船舶退火既不是必要的也不高效。此外,根据微机械建模考虑和BR3和YA1板的支持性三点慢速弯曲的夏状测试,在CVN冲击试验中对41焦耳的吸收能量水平指向41焦耳的吸收能量水平的实践是挑战。最后,讨论了脆化,退火和退火后重新叙事对照射温度,镍和其他合金化或杂质元素的敏感性,以证明降低这些材料的调节处方的保守主义。

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