Programme And Module Handbook
 
Course Details in 2025/26 Session


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Module Title LM Reactor Safety and Analysis
SchoolPhysics and Astronomy
Department Physics & Astronomy
Module Code 03 26459
Module Lead Prof Paul Norman
Level Masters Level
Credits 10
Semester Semester 1
Pre-requisites
Co-requisites
Restrictions None
Exclusions
Description The module covers the key areas of economics of nuclear power and safety of a variety of reaction types and designs. The detailed contents are:

Economics of nuclear power: Breakdown of cost and factors affecting it. Comparison with fossil-fuelled plant. World-wide distribution of the reactors and their relative advantages and disadvantages. Possible future developments.

Graphite moderated reactors: Magnox reactors: Factors affecting choice of fuel, cladding and moderator. Materials and safety factors affecting temperature and performance. Overall factors affecting thermal efficiency. Emergency shut-downand core-cooling plant. Effects of depressurisation accident. Consequences of onload refuelling. Steel oxidation.

AGRs: Ways in which this reactor overcomes the limitations of Magnox systems. Differences in design arising from different fuel and higher gas temperatures. Fuel and moderator design and performance; radiolysis and graphite corrosion. Emergency shut-down systems.

HTGRs: Construction of fuel microspheres and core layout. Fission product retention.Temperature limitations and possible use for process heat plant. Water moderated reactors: PWRs: Main features of plant, including layout and containment. Reactivity control with chemical shims, the Chemical and Volume Control System. Power defect and load-following. Consideration of safety of thick steel vessels. Auxiliary shut-down and emergency core-cooling plant. Loss-ofcoolant accidents. Radiolysis and zirconium interaction with water. The Sizewell B design. Use of MOX in PWR plant.

BWRs: Differences between PWR and BWR systems and effects on performance and safety e.g. effect of steam on design and operation. Emergency core cooling. Primary containment philosophy.

CANDU and SGHWR: Similarities and differences between the two systems. Advantages of use of D2O and of pressure tube designs; fabrication and problems of pressure tubes. Emergency core cooling. Uranium utilisation.

Other reactor systems: Graphite-moderated but water cooled reactors (e.g. the RBMK, Chernobyl type). Mixed oxide fuels. Fast breeder reactors: Possible breeding cycles. Factors affecting choice of fuel and coolant. Design features arising from use of liquid sodium. Effect of sodium voiding. Overall plant layout. Special instrumentation. Doubling time and breeding ratio.

Reactor safety: Methodology of event-tree and fault-tree analysis. Statistical data on component failure rates. Safety related engineering studies. The role of the Nuclear Installations Inspectorate and concepts of Tolerability of Risk. Problem of human intervention. Dispersion analysis; effects of weather, siting and population distribution. Role of instrumentation; redundant logic and fail-safe systems. Discussion of main features and conclusions of the Rasmussen Report. Analysis of the Three Mile Island and Chernobyl accidents.
Learning Outcomes By the end of the module the student should be able to:
  • understand the economic and saftey factors involved with a variety of reactor designs as described in the module description.
Assessment 26459-01 : Exam : Exam (Centrally Timetabled) - Written Unseen (100%)
Assessment Methods & Exceptions Class Test (20%); 1.5 hours Examination (80%)
Other
Reading List