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CRUD in PWR/VVER and BWR Primary Circuits

BWR Chemistry, Coolant Chemistry & Corrosion

The objective of this report is to provide members with the basic understanding of the mechanisms involved and their relationship to material performance and activity buildup. Content of the report is outlined below.

  • Fuel cladding failures due to accelerated corrosion
  • Axial Offset Anomaly (AOA)
  • Pressure drop problems especially in CANDU-plants and VVER units
  • Build-up of out-of-core radiation fields
  • Shutdown extensions due to high activity releases (Coolant clean-up)
  • Increased generation of radioactive waste
  • Interference with inspection necessities

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Effect of Zink in BWR and PWR/VVER on Activity Build-Up, IGSCC and Fuel Performance

BWR Chemistry, Coolant Chemistry & Corrosion, PWR/VVER Chemistry

This Report gives a comprehensive understanding of the zinc chemistry mechanism and information on how Zinc Chemistry in BWR and PWR plants was introduced in the plants and explains the results achieved. This information is useful not only for utilities that are intending to apply Zinc Chemistry in the near future in their plants and for selecting strategies for adding zinc; but also for those utilities that are already applying Zinc Chemistry in order to optimize their strategy based on international experience. It will also be useful for Manufacturers and Regulators.

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Introduction to Boiling Water Reactor Chemistry

BWR Chemistry, Coolant Chemistry & Corrosion

VOLUME II
This report is the second volume out of two focusing on BWR chemistry. This volume II takes a closer look at corrosion of structural materials covering the following topics:

  • Corrosion Considerations
  • Stress Corrosion Cracking Mitigation
  • Start-up IGSCC Mitigation
  • Shutdown Dose Rate Minimization
  • Reactor Water Purity Transients
  • Surveillance Programs

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Introduction to Boiling Water Reactor Chemistry

BWR Chemistry, Coolant Chemistry & Corrosion

VOLUME I
This report is the first volume out of two focusing on BWR chemistry. A review and discussion of the BWR chemistry fundamentals that are necessary to understand and describe the requirements of the BWR water specifications is provided in this volume. This discussion includes the basics of water radiolysis, the dynamic process that establishes the concentration of oxygen and hydrogen gas in the reactor water, the consequences of tramp uranium and leaking fuel rods on chemistry and other relevant topics.

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

Annual Reports Presenting Key Results Published During 18 Months, Structural Material Degradation

(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

Annual Reports Presenting Key Results Published During 18 Months, Structural Material Degradation

(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 Relating to Structural Materials Degradation

Degradation of Different Types of Structural Materials, Structural Material 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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