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Structural Material Degradation

View allDegradation of Different Types of Structural MaterialsAnnual Reports Presenting Key Results Published During 18 Months
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The condenser: a key player for a good feedwater chemistry

This report compiles the degradations observed in condensers, either on steam side or raw water side. The oldest condensers were known before the nuclear era, the newest came to the light with the development of nuclear reactors. However, more attention was brought to nuclear plant condensers since while operating with a few leaks was allowed in fossil fired plants, this was strictly forbidden in pressurized water reactors, mainly because of the steam generators susceptibility to pollution.

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PWRs Operation and Maintenance Raw Water Systems (LCC19)

Raw water has a major safety role as acting as cold source for plants. Raw water is used for:

  • Cooling the condenser, either in open or in closed circuits;
  • Providing water for service water systems;
  • Providing water to the Fire Fighting System;
  • Providing water to the Auxiliary Feedwater Tank in case of emergency (earlier units).

The report covers the following topics: design consideration, raw water chemical treatments, operating experience along with the maintenance programmes of raw water systems.

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Key Results From Recent Conferences on Structural Materials Degradation in Water Cooled Reactors

This report reviews the key papers published in the following conferences:

  • The 14th International Conference on “Environmental Degradation of Materials in Nuclear Power Systems”, Virginia Beach, USA, August 24–28, 2009.
  • The Fontevraud 7 Conference “Contribution of Materials Investigations to Improve the Safety and Performance of LWRs”, Avignon, France, September 26–30, 2010.
  • Jubilee day seminar on “Stress Corrosion Cracking of Nickel Base Alloys at CEA – Coriou Effect”, Saclay, France, January 26, 2010.

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Key Emerging Issues and Recent Progress Relating to Structural Materials Degradation

(LCC10 AR)
This Report discusses the PWR/VVER highlights from the latest of these conferences, namely the 16th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, that was held in Ashville, NC in August 2013. The corresponding BWR highlights were presented in one of the LCC9 Reports last year. Over 150 papers were published at this conference and covered diverse topics touching on specific degradation modes in various alloys. Additionally, journal articles appearing on the same subjects in the technical literature in the last two years are also reviewed.

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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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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

(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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