OTHER TOPICS

COOLANT CHEMISTRY & CORROSION

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

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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CRUD in PWR/VVER Coolant Volume II – Control of CRUD in the PWR/VVER Coolant and Mitigation Tools

(LCC11 STR)
All materials used in nuclear power plants, as bare material (steels and alloys), are not stable in the reactor water and dissolve by corrosion. They are protected by passive oxide layers formed by the corrosion attack of the water to the metal surface under operating conditions. However, to some small extent these oxide layers dissolve in the reactor coolant and are transported as corrosion products (called also CRUD) to the reactor core. There they deposit on the fuel assemblies and are activated. The deposition of the crud on fuel assemblies and their release to the coolant highly influences the core and plant performance with respect to fuel cladding integrity and radiation fields.

The purpose of the Volume II of this Report, in LCC11, is to describe the tools and their application to adequately control the coolant crud in order to improve the fuel and out-core radiation performance. This information can support the plant chemists to establish strategies of applying the mitigating tools for crud control to achieve their plant specific goals. The information given in this Report is also valuable for fuel vendors and plant fuel engineers to evaluate the possible ways of improving the fuel performance. In a similar way, this information helps the Regulators at properly examining the relative importance of various CRUD Control Mitigating Tools to ensuring an improved fuel performance for safe operation. 
The associated Volume I containing: Mechanism of Sources, Transportation in Coolant, Fuel Deposition and Radiation Build-up, was published within the LCC10 Programme.

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CRUD in PWR/VVER Coolant. Volume I – Sources, Transportation in Coolant, Fuel Deposition and Radiation Build-Up

Crud in PWR/VVER Coolant. Volume I – Sources, Transportation in Coolant, Fuel Deposition and Radiation Build-up (LCC10 STR) The topic is covered in two separate volumes. Volume I which is provided within the LCC10 Programme, and Volume II which will be provided in the LCC11 Programme. This document, Volume I covers the following topics:

  • Introduction
  • Sources of CRUD
  • CRUD Transportation in PWR/VVER Coolant
  • Crud Deposition in the Core
  • Crud Release from Core and Radiation Build-up Mechanism
  • Summary Volume II will contain information on Control of CRUD in the PWR/VVER Coolant and Mitigation Tools

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Decontamination and Steam Generator Chemical Cleaning

(LCC5 STR)
The objective of this Report is to help the reader to gain a basic understanding of the mechanisms involved in the Decontamination and the Steam Generator Chemical Cleaning Processes. The processes described do not only deal with the basic description but also with application considerations. A second approach to Decontamination is a chronology of the plant applications which range from components to subsystem and full system Decontamination.

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Deposit Formation on Fuel Cladding in PWR Primary Systems

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

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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Historical and Present Issues on Secondary System Chemical Treatment and Corrosion in PWR/VVER Units; including Materials Behaviour

(LCC15)

This report describes and explains the past and present issues related to secondary system chemistry and materials behaviour.
It starts with the relation between design and material evolution influence on chemistry selection, as well as guidelines for the secondary system. It also explains the behaviour of added reagents and of impurities in the secondary system. The integrity and long-term behaviour of the plant is largely considered.

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Historical Evolution of Coolant Chemistry for PWR/VVER Plants: 1960 to Present; Including Basis of the Guidelines

(LCC15)

This report describes the historical development of the water chemistry in primary side of the PWR and VVER plants since 1950s up to present. Starting with the first research PWR plants in USA without applying any water chemistry addition of neither alkaline reagent nor hydrogen, lot of fuel performance degradations were experienced in 1950s and 1960s, such as heavy fuel deposits, flow restrictions across the core, reactivity losses and high radiation fields. Even the first AOA indications were experienced in a PWR with low core duty operating without applying water chemistry treatment.

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Incoming Goods, Hazardous Materials and Aging of Plant Chemicals

The objective of this Report is to provide a comprehensive understanding of controlling the quality of incoming goods in Nuclear Power Plants. The Report will help utilities with checking that their Quality Assurance system is appropriate or modifying it. The Report will also be useful for manufacturers at properly implementing manufacturing, protection, shipping, labelling, etc for avoiding degradation that may be discovered at the very beginning of plant operation. Finally, regulators will have a complete view of the possible risks of degradation and how to verify that the Quality Assurance programs are implemented.

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