首页> 外文会议>Symposium on Small Specimen Test Techniques: Fourth Volume; Jan 23-25, 2000; Reno, Nevada >Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels
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Application of the Reconstituted Subsize Specimens for Assessment of Irradiation Embrittlement of RPV Steels

机译:重构的亚尺寸试样在RPV钢辐照脆性评估中的应用

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The actual values of the weld metal characteristics required for determination of the RPV lifetime, that is the ductile-to-brittle transition temperature (DBTT) in the unirradiated condition (T_(ko)), the phosphorus and copper contents (that are known to affect the radiation stability of steel), were not measured during manufacturing of old VVER-440 reactors. The small samples (templets) were cut out of the inside surface of the old Russian VVER-440 reactor pressure vessels (RPV) to assess the actual condition of the RPV material before and after post-irradiation annealing and after re-irradiation. Calculations have shown that it is not admissible to cut out samples of the size appropriate for machining of fullsize Charpy specimens necessary to comply with Russian Guide for determination of RPV steel DBTT. An application of subsize specimens for estimation of irradiation embrittlement of RPV steel was substantiated. In order to substantiate application of reconstituted subsize specimens made from broken subsize specimens for assessment of irradiation embrittlement of RPV materials, the correlation dependencies between the DBTT values of reconstituted and standard subsize specimens were developed. With this aim reconstitution of broken 5x5x27.5 mm specimens was performed by the stud-welding method. Both unirradiated and irradiated to high fluence steels were used in this program. The influence of reconstitution on the correlation dependence of DBTT for standard fullsize and subsize impact specimens was studied. Irradiation and re-irradiation kinetics of RPV steels were studied using subsize specimens machined from templets of operating units.
机译:确定RPV寿命所需的焊接金属特性的实际值,即未辐照条件下的韧性到脆性转变温度(TTT(ko)),磷和铜含量(已知影响钢的辐射稳定性),在制造旧的VVER-440反应堆时未进行测量。从旧的俄罗斯VVER-440反应堆压力容器(RPV)的内表面切下小样品(模板),以评估RPV材料在辐照后退火前后和再辐照后的实际状况。计算表明,不允许切出适合于加工全尺寸夏比(Charpy)样品的尺寸合适的样品,以符合确定RPV钢DBTT的俄罗斯指南的要求。证实了小尺寸试样在RPV钢辐照脆性评估中的应用。为了证实由破碎的子尺寸样本制成的重构子尺寸样本在评估RPV材料的辐射脆化中的应用,开发了重构子和标准子尺寸样本的DBTT值之间的相关性。为了这个目的,通过螺柱焊接方法重建了破碎的5×5×27.5mm的样品。在此程序中使用了未辐照和辐照高通量钢。研究了重构对标准全尺寸和小尺寸冲击试样的DBTT相关性的影响。 RPV钢的辐照和再辐照动力学是使用操作单元模板加工的小尺寸试样进行研究的。

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