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首页> 美国政府科技报告 >Stress Corrosion Cracking of Alloy 600 and Alloy 690 in All Volatile Treated Water at Elevated Temperatures. Final Report (PWR)
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Stress Corrosion Cracking of Alloy 600 and Alloy 690 in All Volatile Treated Water at Elevated Temperatures. Final Report (PWR)

机译：高温下所有挥发性处理水中合金600和合金690的应力腐蚀开裂。最终报告（pWR）

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This report describes a continuing study of stress corrosion cracking (SCC) of Inconel alloys 600 and 690 in all-volatile treated (AVT) water. Specimens of alloys 600 and 690 are being exposed to AVT water at 288 exp 0 , 332 exp 0 , 343 exp 0 , and 360 exp 0 C. Alloy 600 generally resists SCC in high-purity water under normal service conditions but is susceptible under other specific conditions. In general, mill-annealed alloy 600 is more susceptible than stress-relieved material. Susceptibility to SCC increases rapidly with increasing exposure temperature. Very high stresses (near or above yield) are required to induce cracking in AVT or other high-purity waters. Most of the data presented in this report are for alloy 600; alloy 690 has not yet cracked. However, the program is being continued and will subsequently characterize the high-purity water cracking behavior, if any, of alloy 690. (ERA citation 08:035807)

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