首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems-water reactors >STRESS CORROSION CRACKING OF STAINLESS STEELS TESTED BY DYNAMIC LOADING IN OXIDIZING AND REDUCING PWR PRIMARY ENVIRONMENT
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STRESS CORROSION CRACKING OF STAINLESS STEELS TESTED BY DYNAMIC LOADING IN OXIDIZING AND REDUCING PWR PRIMARY ENVIRONMENT

机译:在氧化和还原压水堆主要环境中通过动态载荷测试的不锈钢应力腐蚀开裂

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Austenitic stainless steels (SS) are widely used for LWR component manufacturing. The field experience of Type 304, 316, 316 Ti and 347 austenitic stainless steels and their L grade in PWR primary circuits has been generally outstanding. However, a recent review made by EPRI of all known SCC of SS exposed to PWR primary environment indicates that almost 80% of the Operational Experience (OPEX) occurred in low flow or stagnant zones in dead leg situations where the primary water chemistry was probably contaminated by anionic impurities especially trapped oxygen bubbles in the case of Canopy Seals. Further, the radiolysis in closed volumes such as blind-end holes with limited or no ingress of conditioned hydrogenated PWR primary coolant may lead to increased REDOX-potentials. Oxygenated PWR primary water transients could also be a potentially important factor in the in-service failures that have occurred in cold worked stainless steels in PWRs. Indeed, oxygen ingress can occur under a variety of circumstances such as load following if aerated feed water is injected while deborating the primary coolant. A dedicated program based on SSRT tests was designed to evaluate the PWSCC susceptibility at 345°C of type 316L austenitic stainless steel. Three different environments were chosen; two oxidizing PWR primary environment with 10 ppm and 0.1 ppm of dissolved oxygen and a reducing nominal PWR primary environment with a hydrogen partial pressure of 0.3 bar.
机译:奥氏体不锈钢(SS)被广泛用于轻水堆零部件的制造。通常,PWR一次回路中304、316、316 Ti和347型奥氏体不锈钢及其L级的现场经验非常出色。但是,EPRI最近对暴露在压水堆主要环境中的所有已知SS的SCC进行的审查表明,几乎80%的操作经验(OPEX)发生在死水情况下的低流量或停滞区域,在这些情况下主要水化学物质可能已被污染阴离子杂质,特别是在冠层密封件的情况下被捕获的氧气气泡。此外,在封闭空间(如盲孔)中进行的辐射分解可能会限制或完全不会使经过调节的氢化PWR主冷却剂进入,从而导致REDOX电位升高。氧化的PWR初级水瞬态也可能是压水堆冷加工不锈钢在使用中发生故障的潜在重要因素。实际上,在多种情况下都可能发生氧气进入,例如在注入负荷的给水同时使主要冷却剂脱硼的情况下跟随负荷。设计了一个基于SSRT测试的专用程序,以评估345L型316L奥氏体不锈钢在PWSCC中的磁化率。选择了三种不同的环境。具有10 ppm和0.1 ppm溶解氧的两个氧化PWR主环境和具有0.3 bar氢气分压的还原型标称PWR主环境。

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