首页> 外文会议>International High-Level Radioactive Waste Management 2019 >NEUTRON RESIDUAL STRESS MAPPING OF REPAIRED SPENT NUCLEAR FUEL WELDED STAINLESS-STEEL CANISTERS
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NEUTRON RESIDUAL STRESS MAPPING OF REPAIRED SPENT NUCLEAR FUEL WELDED STAINLESS-STEEL CANISTERS

机译:修复的核燃料油焊接不锈钢罐的中子残余应力映射

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Abstract: Stress corrosion cracking (SCC) caused byatmospheric deposition and deliquescence of aggressivecompounds such as chloride-containing salts or oxidizedsulfur species may pose a potential issue to the extendedservice life of spent nuclear fuel (SNF) storage canisters.When a chemically susceptible material is exposed to ahostile environment (e.g., coastal salt air) for a sufficientlength of time, SCC may occur at locations on the canisterwhich have undergone high tensile residual stress. Theselocations are often found in weld zones and the heataffectedzones (HAZ) of welded joints. Ideally, these crackscould be repaired by traditional fusion welding techniques,but the highly localized heat input of the repair weldingmay introduce additional high tensile residual stress andcould increase the risk for future SCCs. This paperpresents the results of neutron residual stress mapping ofas-welded and repaired stainless steel specimens. The asweldedspecimens were provided by Sandia NationalLaboratories from a canister mock-up manufactured usingprocedures similar to those used for actual canisterproduction. ASME-qualified gas-tungsten arc welding(GTAW) was used to repair the specimens, and post-repairresidual stresses were measured using neutron diffractionat the Oak Ridge National Laboratory (ORNL) High FluxIsotope Reactor (HFIR). As-welded and repaired specimenresidual stress distributions are evaluated and compared.Significant residual stress profiles were identified from thereceived as-welded longitudinal weld sample. Thegenerated residual stress profile from neutron diffractionis similar to that of the Sandia residual stress data obtainedfrom deep-hole drilling. The GTAW-repaired specimenshowed a notable redistribution in residual stresses andeven introduced compressive stresses when compared withthe as-welded condition. It appears that groove excavationand the well-controlled GTAW heat input resulted in astress relief/annealing effect on the metal. The results ofthis comparison are expected to be used to guideimprovements in future repair welding techniques.
机译:摘要:大气中的沉积物和潮气性化合物如含氯化物的盐或氧化的硫磺化合物引起的应力腐蚀开裂(SCC)可能会延长其使用寿命。乏核燃料(SNF)储存罐。\ r \ n当化学敏感材料暴露于敌对环境(例如沿海盐雾)中足够长的时间后,SCC可能会在已承受高拉伸残余应力的罐。这些位置通常在焊接区和焊接接头的热影响区(HAZ)中发现。理想情况下,可以使用传统的熔焊技术来修复这些裂纹,\ r \ n,但是修复焊接的高度局部热量输入\ r \ n可能会引入额外的高拉伸残余应力,并且\ r \ n可能会增加未来SCC的风险。本文介绍了焊接和修复后的不锈钢样品的中子残余应力测绘结果。焊接的样品是由Sandia National \ r \ nLaboratories通过使用类似于实际罐子生产过程的罐子模型制造的罐子模型提供的。使用ASME认证的钨极氩弧焊\ r \ n(GTAW)修复标本,并使用中子衍射\ r \ nat橡树岭国家实验室(ORNL)高通量测量修复后的残余应力\ r \ n \ r \ n同位素反应堆(HFIR)。评估并比较了焊接后和修复后的试样\ r \残余应力分布。\ r \ n从\ r \ n收到的焊接纵向焊缝样品中识别出了显着的残余应力分布。中子衍射产生的残余应力轮廓与从深孔钻探获得的桑迪亚残余应力数据相似。与焊接条件相比,GTAW修复后的试样在残余应力方面表现出显着的重新分布,并且甚至引入了压缩应力。看来,开挖沟槽和良好控制的GTAW热输入会导致对金属的应力消除/退火效应。该比较的结果有望用于指导未来维修焊接技术的改进。

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    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831 chatzidakiss@ornl.gov;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

    Oak Ridge National Laboratory, One Bethel Valley Road, Oak Ridge, TN 37831;

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