首页> 外文会议>ASME Pressure Vessels and Piping Conference >ROOT CAUSE ANALYSIS OF THE UNEXPECTED BEHAVIOUR OF A FLAKED MATERIAL UNDER IRRADIATION AND TRANSFERABILITY TO THE DOEL3/TIHANGE2 REACTOR PRESSURE VESSELS
【24h】

ROOT CAUSE ANALYSIS OF THE UNEXPECTED BEHAVIOUR OF A FLAKED MATERIAL UNDER IRRADIATION AND TRANSFERABILITY TO THE DOEL3/TIHANGE2 REACTOR PRESSURE VESSELS

机译:在辐照下剥落材料的意外行为的根本原因分析,与DOEL3 / Tihange2反应器压力容器的辐照和可转移性

获取原文

摘要

During the 2012 outage at Doel 3 (D3) and Tihange 2 (T2) Nuclear Power Plants (NPP), a large number of nearly-laminar indications were detected mainly in the lower and upper core shells. The D3/T2 shells are made from solid casts that were pierced and forged. Restart authorization in 2013 was accompanied by a number of "mid-term" requirements, to be completed during the first operating cycle after the restart. One of these requirements was the mechanical testing of irradiated specimens containing hydrogen flakes. These tests showed unexpected results regarding the shift in the Reference Temperature for Nil Ductility Transition (RT_(NDT)) of the flaked material VB395 (Steam Generator shell rejected because of flakes) after irradiation. This paper presents the root cause analysis of this unexpected behaviour and its transferability (or not) to the D3/T2 Reactor Pressure Vessels (RPVs). A mechanistic and a manufacturing based approach were used, aiming at identifying the microstructural mechanisms responsible for the atypical embrittlement of VB395 and evaluating the plausibility of these mechanisms in the D3/T2 RPVs. This work was based on expert's opinions, literature data and test results. Both flaked and unflaked samples have been investigated in irradiated and non-irradiated condition. All hydrogen-related mechanisms were excluded as root cause of the unexpected behaviour of VB395. Two possible mechanisms at the basis of the atypical embrittlement of VB395 were identified, but are still open to discussion. These mechanisms could be linked to the specific manufacturing history of the rejected VB395 shell. Since the larger than predicted shift in transition temperature after irradiation of VB395 is not linked with the hydrogen flaking and since none of the specific manufacturing history features that are possible root causes are reported for the D3/T2 RPVs, the D3/T2 shells should not show the unexpected behaviour observed in VB395.
机译:在DoEl 3(D3)和Tihange 2(T2)核电厂(NPP)的2012年停电期间,主要在下部和上芯壳中检测到大量的近层次迹。 D3 / T2壳由固体铸件制成,刺穿和锻造。重新启动2013年的授权伴随着许多“中期”要求,在重启后的第一个运行循环中完成。其中一个要求是含有氢薄片的辐照样品的机械测试。这些测试显示出意外结果,关于剥离材料VB395(由于薄片被拒绝的蒸汽发生器壳被拒绝)的蜗杆延展性转变(RT_(NDT))的参考温度的变化(蒸汽发生器壳被剥落)。本文介绍了这种意外行为的根本原因分析及其转移(或不)到D3 / T2反应器压力容器(RPV)。使用机械和基于制造方法,旨在鉴定负责VB395的非典型脆化的微观结构机制,并评估D3 / T2 RPV中这些机制的合理性。这项工作是基于专家的意见,文学数据和测试结果。已经在辐照和非照射条件下研究了剥落和未杂种样品。所有氢相关机制都被排除为VB395意外行为的根本原因。确定了基于VB395的非典型脆化的两种可能的机制,但仍然讨论。这些机制可以与拒绝的VB395壳的特定制造历史相关联。由于VB395照射后的转变温度的预测变化没有与氢剥落没有连接,因此对于D3 / T2 RPV的可能根本原因的特定制造历史特征无关,因此D3 / T2壳体不应显示VB395中观察到的意外行为。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号