Development of a Radioactivity Transport Code to Support the CANDU Industry

Knowledge of corrosion products and radioactivity transport in nuclear reactors is necessary to minimize radiation dose to station workers during maintenance activities. Modelling radioactivity transport can also be used predictively to assess how changes to station chemistry affect radiation fields.
The objective of this project is to develop a new code in Python, leveraging the layout and validated mechanisms of previously developed codes at the Centre for Nuclear Energy Research at the University of New Brunswick and at Canadian Nuclear Laboratories, respectively, followed by using the new platform for further development. To support continued, nuclear-based clean energy production in Canada, this code will model multiple Canadian station configurations without requiring multiple code versions.

Faculty Supervisor:

Olga Palazhchenko

Student:

Partner:

Canadian Nuclear Laboratories

Discipline:

Engineering

Sector:

Professional, scientific and technical services; Public administration; Utilities

University:

University of New Brunswick

Program: