Structural Materials Degradation Seminar

Continuous evidence of the necessary precautions in sense to ensure performance and integrity are the most important duties of nuclear power plant operators. Those efforts should be applied to major systems, structures, and components SCCs important to safety. The operating organisation shall be aware of possible consequences in case of failure and determine needful activities.

In the past some severe incidents (Davis Besse, Mihama, V.C. Summer) happened which are linked with grave materials degradations so loss of function or integrity occurred. From these incidents the nuclear industry has drawn consequences and improved their safety culture.

SEMINAR OBJECTIVE:

The planned A.N.T. International Academy Seminar follows previous seminars offered by A.N.T. International on aspects related to degradation experienced by nuclear reactor components. The objective of the 3-day Seminar is to give an overview of the world wide operational experience with major SCCs in nuclear power plants (PWR, BWR). Herby various examples of safety-related reactor components are presented suffering degradation due to specific ageing mechanisms. Measures to prevent failure and precautions to maintain component performance and integrity to ensure long term operation are presented.

An attendee of the seminar will gain:

1

Enhance the awareness and provide practical information relevant to implement component monitoring and addressing ageing in nuclear plant operation, including the current status of non-destructive examination methods used.

2

Provide practical information on previously experienced ageing of components including, but not limited to, reactor pressure vessel (RPV), piping, nozzles, steam generator tubes, and dissimilar metal welds that accompany such components and others.

3

Present mitigating concepts in case of degradation incidents.

THE FOLLOWING TOPICS ARE COVERED

  • Brief description of the various types of LWRs and of their main components relevant for safety
  • Materials and materials properties
  • Review of Non Destructive Testing technologies used in LWRs
  • WENRA Safety Reference Levels, Issue I “Ageing management”
  • Field experience with PWR components
  • Field experience with BWR components
  • Mitigating concepts in case of degradation incidents (BWR)
  • Degradation in LWR components and Mitigation Techniques
  • Operational surveillance and measures to maintain component performance or reduction of dose rate
  • Brittle fracture analysis of RPV in case of PTS (pressurised thermal shock) in PWR
  • Integrity concept for piping systems with corresponding leak and break postulates in LWR to ensure long term operation

ADDITIONAL DETAILS

SEMINAR INFORMATION:

Download PDF

LECTURERS:

Mr. François Cattant and Dr. Ulf Ilg

DIFFICULTY LEVEL

Basic

DATE AND LOCATION:

March 2019, Palma de Mallorca, Spain

DURATION:

3 days

ASSOCIATED LITERATURE:

Not available

OTHER SEMINARS

Radiation Effects on Material Properties

(2 days, March 7-8, 2019)

by: Dr. Malcolm Griffiths.

PWR Reactor Design and Operation

(1 ½ days, March 14-15, 2019)

by: Mr. Kenneth Epperson.

Zr Alloy Corrosion and Hydrogen Pickup Mechanisms

(2-days, March 14-15, 2019)

by: Mr. Friedrich Garzarolli, Dr. Clément Lemaignan and Mr. Peter Rudling.