LCC1 Annual Report

The Report covers the following topics:

  • Coolant Quality and Control Issues – PWR Water Chemistry – BWR water chemistry
  • Materials selection for the primary BWR and PWR circuits
  • Primary Circuit Corrosion (BWRs and PWRs) – SCC, PWSCC in PWRs – SCC in BWRs and remedies (HWC, NMCA)
  • Dose Rate Buildup and Control
  • Fuel/Water Chemistry Interaction

DOWNLOAD SAMPLE  | DOWNLOAD PRODUCT SHEET

LCC2 Annual Report

The Report covers the following topics:

  • Coolant Quality and Control Issues – PWR/VVER Water Chemistry – BWR water chemistry
  • Structural Materials Degradation
  • Primary Circuit Corrosion (BWRs and PWRs) – SCC, PWSCC in PWRs – SCC in BWRs and remedies (HWC, NMCA)
  • Dose Rate Buildup and Control (BWRs and PWRs)

DOWNLOAD SAMPLE  | DOWNLOAD PRODUCT SHEET

LCC4 Annual Report

The Report covers the following topics:

  • Nuclear plant primary water chemistry experience (PWR, VVER and BWR)
  • Water chemistry sampling and monitoring (PWR, VVER and BWR)
  • Corrosion product control and sampling technique (secondary side, PWR, VVER)
  • Material degradation management
  • Fuel /water chemistry interaction
  • Behaviour of radiolysis gases in BWRs and PWRs

DOWNLOAD SAMPLE  | DOWNLOAD PRODUCT SHEET

LCC5 Annual Report

The Report covers the following topics:

  • PWR/VVER primary side coolant chemistry
  • BWR coolant chemistry
  • PWR and VVER secondary side chemistry
  • Materials degradation
  • Intergranular stress corrosion cracking and irradiation-assisted stress corrosion cracking of cold worked/irradiated stainless steels in de-oxygenated PWR-type coolants

DOWNLOAD SAMPLE  | DOWNLOAD PRODUCT SHEET

Consequences of Power Uprating

A relatively high percentage of all operating LWRs in the world have implemented or are considering some kind of increase of the power (power uprate). This Report provides a worldwide review of power uprates. Water chemistry and radiology experiences of power uprates are presented separated on BWRs and PWRs. Key issues are identified and discussed and available options to assure maintained or improved conditions at power uprates are presented.

DOWNLOAD SAMPLE  | DOWNLOAD PRODUCT SHEET

Key Emerging Issues and Recent Progress Related to Plant Chemistry/Corrosion in PWR/VVER/CANDU Reactors 2014–2015

(LCC11 AR)
Operational issues with their link to other aspects are of large interest for Utilities as well as Regulators, Designers, Manufacturers and Laboratories. This LCC11 Report is covering two technical aspects dealing with: 1) Recycling of waste in primary coolant and, 2) Secondary water chemistry options and Hide out return of impurities from Steam Generators (SG).

Recycling of primary water wastes, is becoming more important to minimize both chemical and radiochemical releases into the environment. A specific focus is given to Tritium impact since this element is not eliminated by purification systems and thus recycled together with concentrates and distillates.

The secondary side chemistry is one of the key factors that are influencing safety, reliability and particularly availability of PWR and VVER Nuclear Power Plants. This Report gives: 1) all the relevant information to select the best chemistry options with the type and concentration of reagents that are used – with their advantages and disadvantages and, 2) the relation between the chemistry specification at SG blowdown and the various options of secondary treatment and purification systems.

The Hide out process and influencing parameters for different types of chemical elements and Hide Out Return of species from the Steam generators is also covered in this Report.

DOWNLOAD SAMPLE

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.

DOWNLOAD SAMPLE