Radiation Effects on Material Properties Seminar

This course is directed at engineers, physicists and materials scientists with an interest in component behaviour in nuclear reactor cores. The primary aim is to give a practical understanding of how material properties are affected by irradiation and how this impacts the reactor operation and the useful life of a given component in the reactor. The course will provide reactor design engineers and reactor operations staff an appreciation for materials selection in reactor construction and also provide some of the tools needed to predict material property changes that occur over the life of the reactor. The focus will be on radiation effects on material properties; corrosion and other reactions with the coolant will not be addressed.

This is a two-day seminar.

THE FOLLOWING TOPICS ARE COVERED

  • Physical Metallurgy of Metal Alloys Used in Nuclear Reactor Cores
  • Evolution of Microstructure and Effect on Mechanical Properties
  • Tensors and Material Properties
  • Radiation Damage — Spectral Effects
  • Irradiation Creep and Growth of Zr-Alloys
  • Applied Rate Theory
  • Microstructure Analysis Using Diffraction
  • Everything a Reactor Engineer Needs to Know — Zr-Alloys
  • Everything a Reactor Engineer Needs to Know — Ni-Alloys
  • Everything a Reactor Engineer Needs to Know — Steels
  • R&D in Support of CANDU Refurbishment

ADDITIONAL DETAILS

SEMINAR INFORMATION:

PDF coming soon!

LECTURERS:

Dr. Malcolm Griffiths

DIFFICULTY LEVEL

Basic

DATE AND LOCATION:

March 2019, Palma de Mallorca, Spain

DURATION:

2 days

ASSOCIATED LITERATURE:

Not available

OTHER SEMINARS

Structural Materials Degradation

(3-days, March 6-8, 2019)

by: Mr. François Cattant and Dr. Ulf Ilg.

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.