首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems water reactors >CRACKING BEHAVIOR OF IRRADIATED HEAT-AFFECTED ZONE SPECIMENS OF TYPE 304 AND 304L STAINLESS STEEL WELDS IN HIGH-PURITY WATER
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CRACKING BEHAVIOR OF IRRADIATED HEAT-AFFECTED ZONE SPECIMENS OF TYPE 304 AND 304L STAINLESS STEEL WELDS IN HIGH-PURITY WATER

机译:304和304L不锈钢在高纯水中辐照热影响区试样的开裂行为

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Stress corrosion cracking of austenitic stainless steel weldments is of great interest for light water reactors. Due to the high heat input of weld process and post-weld neutron irradiation, weld heat-affected zone could be subject to both sensitized microstructure and irradiation embrittlement. In this work, cracking behavior of irradiated HAZ specimens has been investigated for Type 304 and 304L submerged arc and shielded metal arc welds that were irradiated to 0.75 and 2 dpa. The specimens are either as-welded or thermally-treated at 500"Cfor 24 hr prior to irradiation. Crack growth rates have been measured on 1/4T-CT specimens, and comparisons have been made between as-welded and thermally-treated specimens. Relatively high crack growth rates were observed for all HAZ specimens, but no significant difference is noticed between the as-welded and thermally-treated HAZ specimens. Fracture toughness was measured in these HAZ specimens to evaluate irradiation embrittlement and the effect of post-weld thermal-treatment.
机译:奥氏体不锈钢焊件的应力腐蚀开裂对于轻水反应堆非常重要。由于焊接过程的高热量输入和焊后中子辐照,焊缝热影响区可能同时受到敏化微观结构和辐照脆化的影响。在这项工作中,对于0.75和2 dpa的304和304L型埋弧焊和屏蔽金属电弧焊,已经研究了辐照的热影响区试样的开裂行为。样品在辐照前经过焊接或在500“ C下进行了24小时的热处理。已在1 / 4T-CT样品上测量了裂纹的扩展速率,并在焊接和热处理后的样品之间进行了比较。所有热影响区试样均观察到较高的裂纹扩展速率,但在焊接后和热处理后的热影响区试样之间没有发现明显差异,通过测量这些热影响区试样的断裂韧性来评估辐照脆化和焊接后热影响。 -治疗。

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