Carleton University · MECH 5203

Nuclear Engineering

Credits : 0.5 creditReference year : 2026-27

Description

Reactor design and safety requirement overview; reactor physics, chemistry and engineering, CANDU reactor design and operation; CANDU reactor fuel channels, thermalhydraulics and fuel; reactor safety design and analysis; IAEA and Canadian safety analysis requirements; reactor accidents; nuclear energy policy.

Reference text in its original language

Reactor design and safety requirement overview; reactor physics, chemistry and engineering, CANDU reactor design and operation; CANDU reactor fuel channels, thermalhydraulics and fuel; reactor safety design and analysis; IAEA and Canadian safety analysis requirements; reactor accidents; nuclear energy policy.

    Sources and references

    Dates and sources are retained to help you verify the information. Translations are provided to facilitate reading; the official source governs conditions and requirements.

    Source reference : https://calendar.carleton.ca/grad/courses/MECH/

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