MAT427 Management of the Decommissioning Process

Aims/Description: This module provides a comprehensive introduction to nuclear criticality safety and the management of nuclear criticality safety in facilities, or situations, where fissile materials are encountered outside a nuclear reactor. It is designed to reflect the core competencies specified by the United Kingdom Working Party on Criticality (WPC), and consists of a basic nuclear reactor physics and fuel cycle pre-course reading component (mandatory for students who have not yet completed the N01 module) and a one-week taught component which includes a presentation from a visiting lecturer from industry/government, and an introduction to the use of Monte-Carlo codes for criticality safety analysis. The taught component is followed by a post-course criticality safety assessment that is designed to consolidate knowledge gained during the course and to enable students to join industry with a solid understanding of the criticality safety process.

Staff Contact: STENNETT MARTIN C

Assessment: Course work

Information on the department responsible for this unit (Materials Science and Engineering):

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Teaching timetable

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Teaching methods and assessment displayed on this page are indicative for 2025-26.