Key Issues in Plant Chemistry and Corrosion – PWR, VVER, CANDU – 2018

(LCC14)

This first report on PWRs, VVERs, CANDUs and PHWRs summarises and analyses the results to assess in which specific situation the results are applicable and gives the point of view of A.N.T. International expert. Instead of giving a short summary of each paper presented at the conference, the report covers the key facts, either new or of significant interest for LCC customers.

This is of particular interest to discuss how to consider different presentations that may sometimes give contradictory or conflicting results.
The main examples concern zinc addition into the primary coolant, potential replacement of LiOH by KOH in PWRs as used in VVERS, Film Forming Amines, dispersant addition, hydrazine alternates. The advantages, disadvantages, questions or limitations of new solutions are explained.

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Key Issues in Plant Chemistry and Corrosion in BWRs – 2018

(LCC14)

The second report summarising the BWR related papers and various other subjects is designed to provide updated information with the author’s critique and analysis for the benefit of the LCC customers. The report is expected to be a comprehensive summary document incorporating the latest information on BWR water chemistry and decommissioning that would benefit the operators and regulators, and those who have not been able to attend the NPC 2018 Conference.

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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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A.N.T. International Newsletter | Antenna No. 42, 2018

Newsletter from A.N.T. International No.42, 2018 ZIRAT22/IZNA17 SEMINAR Shanghai, China 2018 The 2018 ZIRAT22/IZNA17 Seminar was kindly hosted by Shanghai Nuclear Engineering Research & Design Institute Co., Ltd, in Shanghai. The 2-day November seminar was opened by Director Mr. Libing Zhu 朱丽兵 and dedicated to Interim Dry Storage of Spent Fuel and given by Dr. Albert…

Cooperation between A.N.T. International and NuSTAR

Cooperation between A.N.T. International and NuSTAR Shanghai NuStar Nuclear Power Technology Co., Ltd. (NuStar) was founded in 2011 by former Shanghai Jiaotong University professors and graduate students. It is the first and currently the only private company in mainland China that focuses on commercial PWR core technology development and service provision. NuStar holds a strong…

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Hydride Reorientation

Hydride orientation has an important effect on fracture toughness of hydride-containing zirconium alloys because hydrides form as approximately linear arrays of platelet-shaped microscopic precipitates with habits on or near the basal planes of the α–Zr matrix in which they form.

This Stand Alone Report (SAR) addresses a key aspect of the issues raised in the foregoing by providing a comprehensive, self-contained and up-to-date review and analyses of the results of studies carried out on the conditions governing hydride orientation in zirconium alloy pressure and fuel cladding tubes used in nuclear reactors. The report combines a detailed theoretical and experimental overview of this subject with the author’s own analyses of these results. These analyses make use of theoretical advances documented in the author’s 2012 book dealing with the effects of hydrogen and hydrides on the integrity of zirconium alloy components. In the author’s 2012 book, emphasis is placed on delayed hydride cracking, which is a localised failure mechanism.

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Use of Film Forming Amines (FFA) in Nuclear Power Plants for Lay-up and Power Operation

(LCC13 AR)
This report presents a new corrosion inhibitor based on film forming amines (FFA), which are often referred to as fatty amines or polyamines. FFA can form a mono-molecular hydrophobic film or layer adsorbed on the metal surfaces, that constitutes a homogeneous protective barrier against corrosion by its water-repellent behaviour. FFA belongs to chemical substances of the class of oligo alkylamino fatty amines, the simplest one being the well-known Octadecylamine (ODA). Due to the volatility of the film forming amine, the whole steam water cycle can be protected. The high affinity to surfaces can lead to a slow removal of surface deposits such as loose magnetite and impurities. FFA’s are successfully used as water treatment additives for several decades, in steam water cycles of the VVER type in Eastern Germany and Russia with positive treatment results.

For several years, AREVA has very successfully applied this treatment using a specific procedure in several PWR plants. The purposes are to control the corrosion product transport into steam generators during power operation and for long time lay-up of whole steam water cycle without using hydrazine. Even in a BWR plant this FFA treatment was applied in several parts of steam water cycle with success. This report explains the mechanism of the FFA chemistry treatment and summarises the published information regarding the application results achieved in western nuclear plants.

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The Underestimated Role of the Oxygen on RCS Component Failures

(LCC13 AR)

PWR chemists may claim that there is no oxygen in the Reactor Cooling System because hydrogen injection suppresses the oxidising species generated by radiolysis. This is why, at EDF, the RCS has no oxygen monitoring. In fact, this assessment is true only if free flowing conditions are considered. The RCS contains many flow-restricted or occluded zones where some chemistry deviations can occur, one being the presence of oxygen.

This report aims to keep the plant chemists alert regarding oxygen tracking, ingress, venting, scavenging, monitoring. It also shows some examples of field failures that occurred because oxygen presence was not anticipated in the environment. This report helps plant engineers understand why they should stay alert regarding oxygen control. The report shows there are several ways to limit oxygen ingress or to scavenge oxygen in the RCS. The oxygen specification may seem stringent, however the failures presented in this report support a non-deviation application of the RCS oxygen specification.

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Strategic Plans for Primary and Secondary Water Chemistry Programmes

(LCC13 AR)

The U.S. requirements for a Strategic Water Chemistry Plan, despite the additional work for plants, has been a benefit to U.S. nuclear utilities. The reasons for this are that it requires plants to consider the balance of plant components and their chemistry considerations to the overall integrity of the steam generator integrity, primary system pressure boundary and the fuel cladding integrity. This not to imply that either U.S. utilities or non-U.S. utilities would not consider these issues in developing their own water chemistry plans. However, these voluntary commitments by the U.S. nuclear utilities has probably reduced the regulatory requirements imposed by the NRC, although this is not known for certain.

This document explains the Objective and Optimisation Methodology of this Strategic Water Chemistry Plan. For the Primary Coolant, it includes the Parameters Impacting or not the Pressure Boundary or Fuel Cladding Integrity. For the Secondary System, it includes the key elements and the components susceptibility and reliability. The report is of benefit to those non-U.S. utilities in developing their own water chemistry programs, both primary and secondary side.

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BWR Decommissioning General Information and Experiences

(LCC13 AR)

Many BWR nuclear power plants have begun decommissioning activities recently after a period of 30 to 40 years, with the final goal of obtaining license termination and getting the property released based on the regulator’s decommissioning regulations and guidelines. The power plants use a variety of strategies for dismantling systems, structures, and components, waste management, and deciding on the future use of the site. Typical activities include safely decommissioning of the plant, minimising radioactive waste generation, fuel removal and storage, license termination and getting the site restored and released. In the US, it is expected that decommissioning will be completed within a period of 60 years.

During decommissioning, plant sites typically use one of three approaches, Immediate Dismantling (DCON), Safe Enclosure (SAFSTOR) or Entombment (ENTOMB). Each approach has its benefits and disadvantages although most plants have used the SAFSTOR approach. The report summarises the publicly available BWR decommissioning general information and experiences with salient features and practices employed in the decommissioning activity including potential costs involved.

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