Handbooks & Reports

Key Emerging Issues and Recent Progress Related to Structural Materials Degradation

(LCC14 AR)

During operation, the materials used for the construction of components react with light water reactor environment and cause component degradation, including cracking at welds and piping. Such degradation is due to irradiation, corrosion, fatigue, and other damage mechanisms, and has remained a severe operational challenge for utilities. Details on such degradation are regularly reported and published in scientific journals and at utility workshops and conferences. Foremost in the latter category are those organised since 1983 by NACE, TMS, ANS and CNS in the Environmental Degradation of Water Reactor Materials.
The Annual Report will contain highlights from the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, which was held in Portland, Oregon in August 2017. It will cover PWRs, VVERs, CANDUs and BWRs.

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EPRI LWRs Material Reliability 2016 Conference

(LCC13 AR)

For many years, EPRI has organised conferences on light water reactors materials reliability. Given there was neither Environmental Degradation nor Fontevraud conferences in 2016, EPRI took the opportunity of providing this conference in 2016. During days 2 to 4, 104 slides were presented in 3 parallel sessions, which covered 18 topics on a whole range of concerns of LWRs.

This ANT report is a summary of some of the most important slides, with little text added. The report contains a summary and a chapter dedicated to the relevance of some results presented for the Industry. This conference brings up-to-date information regarding the latest research, plant experiences, analyses, planning and solutions for increased materials reliability in BWR and PWR components. The report is of interest for engineers in charge of expertise, materials, chemistry, non-destructive testing, fracture mechanics, corrosion, irradiation effects, degradation mitigation, and modelling.

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Key Emerging Issues and Recent Progress related to Structural Materials Degradation (PWRs, VVERs, CANDUs and BWRs)

(LCC12)

During operation, the materials used for the construction of components react with light water reactor environment and cause component degradation, including cracking at welds and piping. Such degradation is due to irradiation, corrosion, fatigue, and other damage mechanisms, and has remained a severe opera­tional challenge for utilities. Details on such degradation are reg­ularly reported and published in scientific journals and at utility workshops and conferences. Foremost in the latter category are those organized since 1983 by NACE, TMS, ANS and CNS in the Environmental Degradation of Water Reactor Materials.

This Report contain highlights from the 17th Inter­national Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, which was held in Ottawa, Canada in August 2015. It covers PWRs, VVERs, CANDUs and BWRs. Over 150 papers were published at this conference and this Report cover diverse topics touching on specific degradation modes in various alloys, such as:

• PWSCC of cold worked Alloy 690 and its weld metals
• Corrosion fatigue of stainless steels in PWRs and BWRs
• Fuel cladding materials
• Cracking of Alloy 718 and X750
• Flow assisted corrosion
• Oxide films and characterisation in PWR Secondary systems
• SCC of Alloy 82 and 182 welds
• IASCC of stainless steels
• Irradiation studies involving ion and neutron irradiation
• Synergistic effects of thermal ageing and neutron embrittlement
• Alloy 600 oxidation and mechanisms in PWRs
• PWR Field experience
• Advances in in-situ monitoring and ex-plant and mockup component evaluation
• Generation IV materials research
• Fundamental studies involving new state-of-the-art microscopy and other techniques
• Fukushima accident related research on SS corrosion in sea water
• Dry Cask Storage System and Waste Container Corrosion

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Key Emerging Issues and Recent Progress Related to Structural Materials Degradation (BWRs and Some PWRs) 2014–2015

(LCC11 AR)
Environmentally-assisted degradation of structural alloys has remained a severe economic issue for utilities operating water cooled nuclear reactors. This Report reviews the key information presented at the “Fontevraud International conference” which was held in Avignon, France, in September 2014. In this conference, research work, related to field failures and issues of various reactor components, is also presented.

This Report addresses the issues of BWRs along with the issues common to some BWRs and PWRs. In addition, this Report summarizes papers in the Civil Engineering (concrete structural material degradation) track as well.
A second associated LCC11 Report reviews the papers relevant to PWRs, some BWR/PWR papers, VVER and CANDU reactors.

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Key Emerging Issues and Recent Progress Related to Structural Materials Degradation in PWRs, VVERs and CANDUs 2014–2015

(LCC11 AR)
Environmentally-assisted degradation of structural alloys has remained a severe economic issue for utilities operating water cooled nuclear reactors. This Report reviews the key information presented at the “Fontevraud International conference” which was held in Avignon, France, in September 2014. In this conference, research work, related to field failures and issues of various reactor components, is also presented.

This Report reviews the papers relevant to PWRs, some BWRs, VVERs and CANDU reactors. 
A second associated LCC11 Report reviews the papers related to BWRs along with the issues common to some BWRs and PWRs.

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