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Deposit Formation on Fuel Cladding in PWR Primary Systems

Coolant Chemistry & Corrosion, PWR/VVER Chemistry

Formation of deposits on Pressurised Water Reactor (PWR) fuel cladding has been an inherent problem in these systems since their inception and remains a problem to-date. The report provides: 1) a brief history of fuel crud in PWR systems, 2) mechanisms for material release, transport and deposition in the core and the influence by material choice, coolant chemistry and core design 3) discussions of what occurs within fuel crud that may affect its deposition rate, its effect on core neutronics and possible impact on clad corrosion leading to failure. Finally, a discussion is given summarizing our current understanding and where future work is required to further this knowledge.

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Corrosion and Hydrogen pickup (HPU) – Vol. III

Corrosion and Hydriding of Zr Alloys, Fuel Material

Corrosion and Hydrogen pickup (HPU) mechanisms of Zr alloys remain a top priority of the nuclear industry. Commercial Zr alloys have today adequate in-reactor corrosion properties. However, hydrogen in fuel components limits the fuel performance today during normal operation and accident conditions as well as during transport of spent fuel. Despite more than 50 years research, the corrosion and HPU mechanisms are still not clear. Improved understanding of the in -reactor oxidation and hydrogen pickup mechanisms are thus required. To shed light on theses complicated mechanisms A.N.T. International has published a set of three reports (Vol. I, II and III) with the focus on explaining the very complicated corrosion and hydrogen pickup mechanisms in an understandable manner.

Volume III gives an introduction to the best understood mechanisms of Zr alloys corrosion and HPU mechanisms, with the aim of giving a ”mental image of the phenomena”, more than discussing in detail all the controversial aspects of the current scientific debates.

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Corrosion and Hydrogen pickup (HPU) – Vol. II

Corrosion and Hydriding of Zr Alloys, Fuel Material

Corrosion and Hydrogen pickup (HPU) mechanisms of Zr alloys remain a top priority of the nuclear industry. Commercial Zr alloys have today adequate in-reactor corrosion properties. However, hydrogen in fuel components limits the fuel performance today during normal operation and accident conditions as well as during transport of spent fuel. Despite more than 50 years research, the corrosion and HPU mechanisms are still not clear. Improved understanding of the in -reactor oxidation and hydrogen pickup mechanisms are thus required. To shed light on theses complicated mechanisms A.N.T. International has published a set of three reports (Vol. I, II and III) with the focus on explaining the very complicated corrosion and hydrogen pickup mechanisms in an understandable manner.

Volume II gives more detailed information on:

  • Early Zr alloy development
  • Out-of-reactor corrosion
  • General in Reactor Corrosion and Hydrogen Pickup behaviour
  • Effects of alloying impurities on corrosion and HPU
  • Corrosion modelling and prediction

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Corrosion and Hydrogen pickup (HPU) – Vol. I

Corrosion and Hydriding of Zr Alloys, Fuel Material

Corrosion and Hydrogen pickup (HPU) mechanisms of Zr alloys remain a top priority of the nuclear industry. Commercial Zr alloys have today adequate in-reactor corrosion properties. However, hydrogen in fuel components limits the fuel performance today during normal operation and accident conditions as well as during transport of spent fuel. Despite more than 50 years research, the corrosion and HPU mechanisms are still not clear. Improved understanding of the in -reactor oxidation and hydrogen pickup mechanisms are thus required. To shed light on theses complicated mechanisms A.N.T. International has published a set of three reports (Vol. I, II and III) with the focus on explaining the very complicated corrosion and hydrogen pickup mechanisms in an understandable manner.

Volume I gives an introduction on the corrosion and hydrogen pickup (HPU) processes in zirconium alloys. The following topics are treated in details:

  • The effects of in-reactor irradiation on both zirconium alloys and the coolant (radiolysis)
  • Crud sources, transport mechanisms and deposition mechanisms
  • Axial offset anomalies
  • Reactor cases of severe crud impact on fuel performance

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The condenser: a key player for a good feedwater chemistry

Degradation of Different Types of Structural Materials, Structural Material Degradation

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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Corrosion Product Generation, Activity Transport and Dose Rate Mitigation in Water Cooled Nuclear Reactors

Coolant Chemistry & Corrosion, PWR/VVER Chemistry

This report discusses in detail, the steps involved in, generation of corrosion products including colloid formation, activation on fuel, transport through the coolant, deposition on surfaces including zeta potential effects, release from surfaces and removal of activated corrosion products in light water reactors. The report also discusses activity transport that will include basic steps involved and models used.

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Zinc Chemistry in PWR Plants from Mid-1990s up to Present: Mechanism and Worldwide Field Experience

Coolant Chemistry & Corrosion, PWR/VVER Chemistry

This updated report reviews, as of 2020, the laboratory and field results of zinc injection technology in PWR plants worldwide. The review covers the range from basic information to current knowledge and understanding of operational behaviour. This information on PWR plants given in this report is also applicable for VVER plants.

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INTERIM DRY STORAGE OF COMMERCIAL SPENT NUCLEAR FUEL

Fuel Material, Fuel Reliability, Interim Dry Storage

This Special Topic Report addresses the degradation mechanisms that could potentially affect the performance of spent fuel stored in a dry, inert environment for periods up to ~100 years. The focus of the review is on the spent nuclear fuel rods, and not on the storage system components such as the casks or the canisters and their internal hardware elements.

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FUEL RELIABILITY ASSESSMENT THROUGH TADIOCHEMISTRY AND POOLSIDE EXAMINATIONS

Fuel Material, Fuel Reliability

The overall objective of this Special Topic Report (STR) is to provide the knowledge of how the reactor environment (fast neutron flux, temperature, water chemistry, etc.) and the Zr-alloy microstructure, which is a function of material chemistry and manufacturing process, impacts fuel performance during normal operations, transients, design basis accidents and interim dry storage.

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