MSc Nuclear Science and Technology / Course details

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. 

The unit aims to:

Provide 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. 

ILO 1

Interpret and explain issues of criticality safety based on systematic knowledge of the physics of criticality, how it is controlled, hazards associated with it, how it is assessed and regulated.

ILO 2

Select and apply appropriate methods to analyse sub-criticality in fissile material containing systems.

ILO 3

Justify analysis through appropriate use of data, benchmarks, cross-comparison, and/or sensitivity analysis.

ILO 4

Assess the critical state, or the degree of sub-criticality, of a facility or plant by application of the range of techniques taught during the course.

ILO 5

Evaluate the criticality safety aspects of a facility and/or process.

ILO 6

Write a coherent and logically-argued technical report in the general style of a criticality safety assessment acceptable to the nuclear industry.

A. Knowledge and Understanding  

Students are taught via directed reading (pre-course) and directly in appropriately equipped rooms at the institution delivering the module. Learning is consolidated in tutorial and review sessions.

Pre-course directed reading                            

Direct Teaching

Review sessions

Tutorial sessions

B. Intellectual Skills

Students are able to exercise their intellectual skills through in-class discussion, tutorial sessions, and the completion of the assigned post-module criticality safety assessment.

In-class discussion

Review sessions

Tutorial sessions

Assignment exercise

Multiple choice questions

Post-course assignment

C. Practical Skills

Students are able to exercise their practical skills through tutorial sessions and completion of the assigned post-module criticality safety assessment.

Tutorial sessions

Post-course assignment

D. Transferable Skills and Personal Qualities

Students are able to enhance their transferable skills through in-class discussion, tutorial sessions, and the completion of the assigned post-module criticality safety assessment.

In-class discussion

Tutorial sessions

Assignment exercise

Post-course assignment 

Review sessions - 0%

Time is allocated in the timetable to review course material in class, to let students integrate the knowledge gained.

Tutorial sessions - 0%

In-class tutorials covering criticality physics and estimating subcriticality

Assignment exercise - 0%

Students work in groups to consider a previous criticality safety assignment and how they would go about addressing it

Multiple choice questions - 0%

Online multiple choice questions covering the range of material in the unit

In-course test - 20%

An in-class test designed to complement the post-module assessment by covering the breadth of material in the course to ensure that students have engaged with the full range of the material. This will take the form of a written test carried out at the end of the taught part of the module. 

Post-module assessment - 80%

A set of questions covering various areas of criticality safety - 20%

and

A comprehensive criticality safety assessment of a hypothetical facility and/or process, or part thereof, involving the processing, storage or use of fissile materials - 60%

Feedback provided in comments on work submitted on Canvas

IAEA Specific Safety Guide SSG-27, Criticality Safety in the Handling of Fissile Material (2014)

Knief, R. A. Nuclear Criticality Safety: Theory and Practice, American Nuclear Society (1985)

McLaughlin, T. P. et al., LA-13638 A Review of Criticality Accidents, Los Alamos National Laboratory (2000)

Bowen, D. G. & Busch, R. D. LA-14244 Hand Calculation Methods for Criticality Safety – A Primer, Los Alamos National Laboratory (2006)