UN805 – Introduction to Operational Health Physics
M.Eng./Diploma Course
Introduction to Operational Health Physics
Dates
January 10, 2027/ January 16-17, 2027/ January 31, 2027/ February 7, 2027/ February 20-21, 2027
Time
9:00 A.M
Location
Hybrid delivery – via Zoom and in person component likely in Whitby or Oshawa (Ontario Tech) – TBC
Instructors
Prerequisites
Course Description
This course introduces students to the core principles of occupational and environmental health physics as applied in the nuclear power, medical, and research fields. Topics include the regulatory framework for radiation safety, essential dosimetric quantities, units and models, and the assessment of doses from both internal and external exposures to ionizing radiation. Students will also examine the key components of an effective radiation safety program and explore environmental exposure pathways relevant to real-world practice.
Important dates
Final exam: March 7, 2027
Assignment #1:
Assignment #2:
Assignment #1:
Last day to drop course :
Preparation
No required preparation
Course Outcomes
Upon completion of this course, students will be able to:
- Explain and apply key dosimetric quantities, units and models.
- Understand the basic framework of Radiation Protection, as defined by the International Commission on Radiation Protection (ICRP)
- Understand Canadian Nuclear Safety Commission (CNSC) Nuclear Safety Act and Regulations, as they pertain to Radiation Protection at a Class I Nuclear Facility.
- Explain and describe the application of the key elements of radiation safety programs for various nuclear facilities and settings.
- Perform basic assessments and analysis required of Health Physicists in a variety of settings, such as: a. Dose estimation for radiological exposure scenarios involving exposure to airborne contamination, surface contamination and / or external radiation hazards, b. Shielding needs assessments, and c. Hazard assessments of protocols involving radioactive materials.
- Understand how to plan radiological work, implement ALARA tools to minimize dose and estimate collective dose.
- Explain how radiological source term changes throughout the life of a nuclear facility and its impact on dosimetry, instrumentation, material release, environmental releases and decommissioning.
- Understand the basic principles of clearing material from radiological areas.
- Determine doses resulting from routine and accidental releases of radioactive material to the environment.
- Establish derived emission limits for nuclear facilities and assessing potential public doses from accidents.