首页> 外文会议>International symposium on zirconium in the nuclear industry >Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)
【24h】

Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)

机译:蒸汽压力对Zircaloy-4和M5熔覆层的高温氧化和冷却后力学性能的影响(LOCA条件)

获取原文
获取外文期刊封面目录资料

摘要

Studies that deal with small and intermediate break loss of coolant accident (LOCA) conditions, for which steam pressure remains relatively high in the reactor primary system, are scarce, even though it has been sometimes observed that steam pressure could have a significant effect on the high temperature (HT) oxidation kinetics of zirconium alloys. Thus, in order to study the effect of steam pressure on the oxidation of low-tin Zircaloy-4 and M5 alloys, cladding samples were oxidized at temperatures between 750 and 1200°C in flowing steam at pressures ranging from 1 to 80 bars. It is shown that the oxidation kinetics of as-fabricated Zircaloy-4 is enhanced under high steam pressure within the 750 to 1000°C oxidation temperature range. The effect is quite low at such temperatures for as-fabricated M5, and at 1100 and 1200°C for both alloys. In order to examine the influence of burn up effects, oxidation tests were performed on Zircaloy-4 and M5 samples pre-hydrided at approximately their respective end-of-life hydrogen expected contents for high bum up claddings and on autoclaved specimens pre-oxidized (pre-existing oxide layer thicknesses from 3 up to 8 μm) at 360°C with typical pressurized water reactor (PWR) primary water chemistry. For both materials, it is shown that pre-hydriding (by gaseous charging) does not significantly modify the oxidation kinetics at 850 and 1000°C (temperatures at which the steam pressure effect is maximal for the fresh materials) under steam pressures of 1 and 80 bars. For the same HT oxidation conditions, the weight gains are lower for the pre-oxidized samples and the differences between sensitivities of Zircaloy-4 and M5 to a pressurized steam environment are significantly reduced after pre-oxidation. No significant hydrogen uptake was observed in the case of M5, whatever the investigated oxidation conditions. Metallurgical observations revealed that the enhanced oxidation kinetics of Zircaloy-4 under high pressure is associated with a significant but limited hydrogen uptake and a thickening of the oxide layers formed at HT. However, it is observed that the diffusion of the oxygen (coming from the cladding oxidation process) through the metallic substrate is not modified. The results show that, for Zircaloy-4 alloy, the steam pressure effect is associated with changes in the oxide microstructure (crystallites morphology, porosity, and cracks). These changes may be, for example, induced by a destabilization of the tetragonal phase of zirconia, so that oxygen and hydrogen transport through the oxide is easier. Ring compression tests performed at room temperature and at 135°C showed that the effect of steam pressure on the post-cooling mechanical properties of fresh, pre-hydrided, or pre-oxidized Zircaloy-4 and M5 samples after transient oxidation at HT is, for the conditions investigated, generally limited, although significant in a few cases for Zircaloy-4. Finally, it was determined that the impact of steam pressure observed for low-tin Zircaloy-4 is very low or negligible on the equivalent cladding reacted (ECR) and the hydrogen pickup of the cladding during typical in-reactor transients and has hence no significant consequence on the verification of LOCA cladding safety criteria.
机译:尽管有时观察到蒸汽压力可能会对冷却剂事故产生重大影响,但很少有研究涉及冷却剂事故的中小断裂损失(LOCA)情况,因为在这种情况下,反应堆主系统中的蒸汽压力仍然相对较高。锆合金的高温(HT)氧化动力学。因此,为了研究蒸汽压力对低锡Zircaloy-4和M5合金氧化的影响,在流动压力为1至80 bar的流动蒸汽中,在750至1200°C的温度下氧化覆层样品。结果表明,在750至1000°C氧化温度范围内的高蒸汽压力下,制成的Zircaloy-4的氧化动力学得到增强。对于这样制成的M5,在这样的温度下,对于两种合金,在1100和1200°C下,其影响都非常低。为了检查燃尽效应的影响,对Zircaloy-4和M5样品进行了氧化测试,这些样品在高沸点熔覆层中的预约寿命分别为预期的氢含量,对预烧化后的样品进行了预氧化处理(使用典型的压水反应堆(PWR)一级水化学物质在360°C时预先存在3至8μm的氧化物层厚度。对于这两种材料,都显示出预加氢(通过气体填充)并不会显着改变在850和1000°C(新鲜材料的蒸汽压力效应最大的温度)和1和1的蒸汽压力下的氧化动力学。 80酒吧。对于相同的HT氧化条件,预氧化样品的重量增加较低,并且预氧化后Zircaloy-4和M5对加压蒸汽环境的敏感性之间的差异显着减小。无论研究的氧化条件如何,在M5的情况下均未观察到明显的氢吸收。冶金观察表明,Zircaloy-4在高压下增强的氧化动力学与显着但有限的氢吸收以及在HT处形成的氧化层的增厚有关。然而,观察到氧(来自覆层氧化过程的)通过金属基板的扩散没有被改变。结果表明,对于Zircaloy-4合金,蒸汽压力效应与氧化物微观结构(微晶形态,孔隙率和裂纹)的变化有关。这些变化可以例如由氧化锆的四方相的不稳定引起,使得氧和氢通过氧化物的传输更容易。在室温和135°C下进行的环压缩测试表明,蒸汽压力对HT瞬时氧化后新鲜,预氢化或预氧化的Zircaloy-4和M5样品的冷却后机械性能的影响为:对于所研究的条件,通常是有限的,尽管在少数情况下对Zircaloy-4具有显着意义。最后,已确定在典型的反应器内瞬态过程中,观察到的低锡Zircaloy-4蒸汽压对等效反应包层(ECR)和包层氢吸收的影响非常低或可忽略不计。对LOCA覆层安全标准进行验证的后果。

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