Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts

DUAN Yuan-gang; XU Bin; TANG Chuan-bao

Jun. 2007

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DUAN Yuan-gang, XU Bin, TANG Chuan-bao. Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts[J]. Nuclear Power Engineering, 2007, 28(2): 62-65.

Citation:

DUAN Yuan-gang, XU Bin, TANG Chuan-bao. Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts[J]. Nuclear Power Engineering, 2007, 28(2): 62-65.

DUAN Yuan-gang, XU Bin, TANG Chuan-bao. Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts[J]. Nuclear Power Engineering, 2007, 28(2): 62-65.

Citation:

DUAN Yuan-gang, XU Bin, TANG Chuan-bao. Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts[J]. Nuclear Power Engineering, 2007, 28(2): 62-65.

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Study on Irradiation-Assisted Stress Corrosion Cracking of Baffle-Former Bolts

National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2006-07-30
Rev Recd Date: 2007-01-26

Available Online: 2025-07-21

Abstract

Abstract

Baffle-Former Bolts in PWR are made of austenitic stainless,locating in the area of strong Neutron irradiation for a long time.When Neutron irradiation exceeds the limit,even if the stress level is very low,the plasticity of the material will lose step by step because of the defects,phase transformation and grain boundary segregation,and then Irradiation-Assisted Stress Corrosion Cracking takes place.Techniques for mitigating IASCC is put forward: using high purity materials,quality control of water,and improvement of structure.
- PWR,
- Baffle-former bolts,
- Irradiation,
- Stress corrosion cracking