NUCLEAR TECHNOLOGY EDUCATION CONSORTIUM REACTOR PHYSICS, CRITICALITY & DESIGN

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1 N01 REACTOR PHYSICS, CRITICALITY & DESIGN Nuclear reactors now account for a significant portion of the electrical power generated world-wide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Reactor physics is the core discipline of nuclear engineering and deals with the physical processes in reactors which are fundamental to the understanding of both operational and safety aspects of nuclear reactors. This module provides a historical background to reactor development, considers the range of possible designs, and explains the underlying nuclear physics principles and models that underpin an understanding of nuclear reactor operations. On completion students should be able to: Compare and contrast the range of nuclear reactor designs, reactor codes, and transport/diffusion theory models used in the industry today. Explain the physical principles which govern criticality, radioactive decay, reactor physics and kinetics, reactor system layout, and underlying nuclear processes which form the basis of how reactors work, run and are modeled in codes. Derive expressions for criticality formulae, diffusion and transport equations for a variety of given situations and layouts. Understand the importance of cross-sections, bucklings, delayed neutrons, six factor formula variables, the function of different parts of a nuclear reactor, and the crucial role played by neutronics in criticality and in the response of a multiplying system. Know some background connected to the historical, environmental, and socio-political aspects of the nuclear industry, and issues related to later decommissioning. Appreciate the need for knowledge of risk assessment, control, and safety for a reactor, and know about some of the consequences and issues connected with historical accidents. History of the industry Environmental and socio-political aspects of nuclear power Reactor design, different reactor types Advanced reactor design Reactor physics, cross sections Nuclear physics and radioactive decay Criticality calculations and neutronics Advanced Reactor Physics and neutron diffusion and transport theory End of life and decommissioning issues Containment and core layout Operational monitoring, reactor control and safety Accidents and risk assessment Reactor physics codes and models

2 N02 NUCLEAR FUEL CYCLE The purpose of this module is to describe the nuclear fuel cycle and examine in detail, the technical, economical, safety and environmental issues involved during each stage. The module covers the entire cycle from the extraction of ore to the disposal of waste. The processes involved in reprocessing of fuel are examined and the consequences reprocessing has, in terms of reactor fuel design and waste disposal, are discussed. Each stage is described on an international scale examining global markets and capacities. On completion, students should have obtained: A full understanding of all the processes involved in the front- and back-ends of the once-through fuel cycle. An understanding of fuel reprocessing and the advantages reprocessing can provide. An appreciation of the safety and environmental considerations involved in the cycle. An overview of the nuclear fuel cycle for commercial purposes and how it has been affected by historic events. Knowledge of the worldwide capacities and economical markets involved in the cycle as well as an appreciation of political influence. Ability to perform some calculations around the economics of the fuel cycle. The key areas covered in this course include: Overview of the fuel cycle Mining and milling of uranium Purification and conversion to UF6 Uranium enrichment Fuel fabrication Properties of irradiated fuel Irradiated fuel transport and storage Nuclear fuel reprocessing Recycling of uranium and plutonium Disposal of nuclear waste Emerging fuel technologies Resource materials and literature references are provided but students should supplement this with their own literature and internet searches.

3 N03 RADIATION & RADIOLOGICAL PROTECTION Explains the properties of different types of radiation occurring as a result of nuclear processes and identifies means whereby levels of radiation and dosages can be detected and measured. The principles of radiation protection and shielding are outlined and demonstrated through practical experience with radioactive sources and detection equipment. The module concludes with an overview of ionising radiation regulations and legislation governing the impact of radiation on people and the environment. The safe handling of accidents is illustrated through case studies of real incidents. On completion, students should have obtained: A full understanding of the sources, types of radiation and hazards associated with nuclear processes Knowledge of radiation detection and monitoring equipment Appreciation of the principles governing the design of radiological protection equipment Understanding of Ionising Radiation Regulations Practical experience of radiation detection equipment The nucleus and nuclear processes Radiation and radiation detection Biological effects of radiation Assessment of radiation exposure Dosimetry Ionising radiations regulations Evaluating the effects of exposure to radiation Practical laboratory: introduction to radiation detectors and monitors Practical laboratory: demonstration of properties of nuclear radiation Case studies safe handling of accidents

4 NUCLEAR TECHNOLOGY EDUCATION CONSORTIUM N04 DECOMMISSIONING/WASTE/ENVIRONMENTAL MANAGEMENT This module focuses upon the environmental and governance aspects of the decommissioning of civil nuclear facilities and radioactive waste management in the UK. The aims of this module are: Firstly, to introduce and develop subject knowledge and theoretical, conceptual and analytical skills in environmental and policy issues and principles associated with nuclear decommissioning and legacy waste management in the UK. Secondly, to provide students with the opportunity to develop and demonstrate subject knowledge and theoretical, conceptual and analytical skills in the application of a Strategic Environmental Assessment, to a topic associated with nuclear decommissioning and legacy waste management in the UK. On completion of this module, students should be able to: Demonstrate an understanding of the scientific, environmental and sociopolitical issues surrounding the decommissioning of nuclear facilities. Understand and critically evaluate the overall environmental principles applicable to plant decommissioning and storage of nuclear waste. Demonstrate an understanding of the principal plant and equipment requirements for processing nuclear waste products. Understand and critically evaluate the impacts of radioactive waste on the environment and community. Demonstrate advanced knowledge and critical understanding of Strategic Environmental Assessments, and an ability to apply that knowledge to case studies in the decommissioning of nuclear facilities and the storage of nuclear waste Demonstrate n awareness of the principal sources of data on environmental and socio-political issues surrounding the decommissioning of nuclear facilities and the storage of nuclear waste, and display an ability to acquire and use that material. This module, which will be delivered at Westlakes Science and Technology Park in West Cumbria, will include lectures on the following topics: Nuclear decommissioning issues and cases Environmental impact assessments Exposure pathways and dose assessments Strategic Environmental Assessments Clean-up, decontamination and remediation Waste disposal and storage options The governance of waste and decommissioning in the UK Social and political issues involved in nuclear facility siting and unsiting

5 Waste inventory calculations Waste packaging and storage Plus guest lectures from the nuclear industry In the second half of the module the student will be working on a case study specifically the Sellafield site Lifetime Plan document. Using the Strategic Environmental Assessment (SEA) process they will focus on the impact of the decommissioning and waste arising issues of that plan, to the environment and the public.

6 N05 WATER REACTOR PERFORMANCE AND SAFETY* Water reactors are likely to be the main source of nuclear power for the foreseeable future. This module considers such reactors with particular reference to their performance and safety and commences with an understanding of water reactor hydraulics, heat transfer and fuel design. The main codes for predicting reactor safety (RELAP, TRAC, CATHARE, TRACE) will also be described as will CFD methods, the latter in the specific context of the generic commercial code, STARCD. Hands-on experience with codes is given. Finally, accidents beyond the design basis ( severe accidents) are discussed. On completion, students should have obtained: A knowledge and understanding of the structure and performance of water reactors A knowledge of the types of accidents which might occur in water reactors and of the steps which are needed to mitigate their consequences A knowledge of the computational bases for establishing water reactor safety The ability to more confidently use reactor performance and safety codes Direct knowledge of CFD methods and their basis, particularly in the context of prediction of water reactor performance and safety Introduction to water reactors Introduction to single phase fluid flow in water reactors Introduction to heat transfer in water reactors Introduction to two-phase flow and heat transfer Calculation of fuel performance Water reactor fuel design Loss-of-coolant accident (LOCA) phenomena Critical flow Introduction to transient system codes Application of the TRACE code Introduction to the STARCD code and its application to water reactor systems Application of the STARCD code Clad ballooning Severe accidents * It is strongly suggested the N12 module (Reactor Thermal Hydraulics) be taken before attempting N05.

7 N06 REACTOR MATERIALS AND LIFETIME BEHAVIOUR This module describes the science and engineering of reactor materials, and the factors that influence the lifetime of these materials, including corrosion and irradiation embrittlement. Other topics covered in this module include fracture mechanics and structural integrity, non-destructive evaluation techniques, as well as plant monitoring and lifetime issues. Also considered are materials specifications and fabrication processes for materials used in nuclear power systems. On completion, students should have obtained: An understanding of the materials science structure/property relationships of key reactor materials, and how these are affected by corrosion and microstructure degradation. An understanding of the methods of structural integrity assessment of reactor pressure vessels. The ability to perform basic structural integrity assessment using the R6 code. An appreciation of the methods of non-destructive testing and plant monitoring. An appreciation of the factors which limit the lifetime of reactor components, such as radiation damage. An appreciation of the specifications and methods of material fabrication for reliable performance in nuclear power system environments. This module consists of lectures, a tutorial and laboratory work. The course content comprises Materials Science and Engineering o Structure and Properties of Metals and Alloys o Corrosion o Graphite Mechanics and Lifetime o Pressure Vessel and Fracture Mechanics o Non-Destructive Testing and Plant Monitoring o Lifetime Issues including Radiation Damage o Materials Specification and Fabrication for high reliability in nuclear power systems The tutorials and laboratory work include: Corrosion Tutorial o Introduction to real examples of corrosion failures Structural Integrity Assessment Tutorial o Introduction to the R6 software through worked examples and problems. Assignments/Grades Students will have a brief pre-course assignment and a post-lecture project dealing with an aspect of Material Degradation in a nuclear power system. There will be a multiple choice test at the end of the week s lectures, and a final examination at a later date.

8 N07 NUCLEAR SAFETY CASE DEVELOPMENT The NTEC N07 Nuclear Safety Case Development module examines the fundamental building blocks and the supporting processes and methodologies used in the formulation of a modern standards nuclear safety case. Within the statutory framework that regulates the nuclear industry, there is an overriding requirement to demonstrate through an adequate and appropriate safety case that all hazards associated with operations on a Licensed Site are understood, effectively managed and controlled. This Module introduces the knowledge and skills necessary to effectively judge and influence the adequacy of licensees nuclear safety cases. On completion, students should: Understand the requirement for a modern standards nuclear safety case; Have an appreciation of the main building blocks of a modern standards nuclear safety case; Have an awareness of the main supporting processes and methodologies used in developing a modern standards nuclear safety case. : This module consists of pre-course reading, a one-week taught component and an assessed post-course assignment. Pre-course reading: HSE Safety Assessment Principles for Nuclear Facilities IAEA Nuclear Safety Tutorials Guidance on application of ALARP Taught: Legislative Requirements for a Nuclear Safety Case Purpose and Scope of a Nuclear Safety Case Nuclear Safety Justification Principles Safety Assessment Principles, Design Standards and Numerical Targets Safety Case Lifecycle Engineering Substantiation Deterministic Safety Analysis Probabilistic Safety Analysis (PSA) Level 1 Consequence Assessment (Level 2/3 PSA) As Low As Reasonably Practicable (ALARP) Safety Case Implementation, Operation, Maintenance and Review. Post-course assignment Preparation of a Preliminary Safety Report for a nuclear facility using scenario data provided.

9 N08 PARTICLE AND COLLOID ENGINEERING IN THE NUCLEAR INDUSTRY Knowledge of particle science is important in a number of technology areas of relevance to the nuclear industry. Particles are used and manipulated throughout the whole nuclear fuel cycle; process improvements are therefore strongly dependent on an understanding of particle behaviour under different conditions. This module will cover all aspects of particle technology that can be considered relevant for the modern nuclear industry. Examples of where particles are relevant within the nuclear fuel cycle will be used to highlight the central importance of this topic area to a nuclear engineer or scientist. On completion, students should: Have a strong understanding of the basics of colloid and particle science Have an appreciation of available methods for modelling particle systems Understand why particle technology is important for the nuclear industry Be able to evaluate current issues and research in the discipline Have the skills necessary to undertake a higher research degree and/or for employment in a higher capacity in industry or area of professional practice; Be capable of independent learning and the ability to work in a way which ensures continuing professional development; critically to engage in the development of professional/disciplinary boundaries and norms. Introduction to particle technology and its relevance to the nuclear fuel cycle Modern particle characterisation techniques Introduction to particle modelling Particle manufacture and its relevance to nuclear fuel manufacturing Solid-liquid systems: aspects of relevance to nuclear waste management

10 N09 POLICY, REGULATION & LICENSING The nuclear industry is one of the most heavily regulated industries in the UK. Regulatory issues necessarily impact upon the development of national policy in environmental and energy areas. This module covers the licensing regime under the Nuclear Installations Act, liabilities arising under international and national law for harm arising from the operation of nuclear facilities, environmental authorisations, transport of radioactive material. The roles of the various regulatory bodies and other players are discussed. The module also addresses the role of the Nuclear Decommissioning Authority, decommissioning of nuclear facilities and UK radioactive waste policies and national strategies. Students are introduced to basic legal principles as applied in the nuclear sector and are shown how to read case law and apply their knowledge to legal problems. On completion, students should: Be able to explain the policy context in which the nuclear industry operates and, in particular, the different views on its contribution to a sustainable energy programme. Be able to list key legal instruments and explain why they have been made. Be able to explain the principles guiding regulation in the nuclear industry and comment on the way that they are used. Be able to describe clearly the governing bodies, nationally and internationally, responsible for formulating policy, promulgating laws and regulations and enforcing them. Be able to explain clearly the responsibility of the employer and the individual in respect of ensuring nuclear safety. Be able to identify the legislation applicable to the student s organisation, and how this is applied. Public bodies involved in determining nuclear policy and regulating the industry at international, European and national levels and the context in which they work. Nuclear Industry Policy and Regulation: Understanding the Realpolitik. Energy Act 2008 and new build. Nuclear Installations Act. Licensing issues Safety assessment, plant justification, engineering substantiation, competency standards. Environmental Permitting Regulations National Strategy for Radioactive Discharges Liabilities: Managing the Nuclear Legacy Energy Act Transport of Radioactive Material. UK Radioactive Waste Policy the MRWS process.

11 N10 PROCESSING, STORAGE AND DISPOSAL OF NUCLEAR WASTES This module reviews basic approaches of nuclear waste management and gives an introduction of scientific fundamentals of nuclear waste processing and disposal. A range of topics will be considered including classification schemes, description of basic techniques of nuclear waste processing, methods of storage and disposal of different types of nuclear wastes. On completion, students should have obtained: A sound understanding of radioactivity, radionuclides and of types of radioactive waste. An appreciation of approaches to nuclear waste management. Knowledge of the encapsulation and immobilisation of waste in a range of wasteforms. A grounding in the techniques of nuclear waste processing to give wasteforms suitable for storage and ultimate disposal. Understanding of general performance and safety assessment methods. Radioactive waste, recycling, waste minimisation and immobilisation. Nuclear decay law. Contaminants and hazard. Heavy metal contaminations. Naturally Occurring Radioactive Materials. Background radiation. Nuclear waste regulations. Principles of nuclear waste management. Sources of nuclear waste Short-lived waste radionuclides. Long-lived waste radionuclides. Basic management approaches and characterisation of radioactive waste. Pre-treatment of radioactive wastes. Treatment of liquid radioactive wastes. Treatment of solid wastes. Hydraulic cements in waste immobilisation. Cementation technology. Immobilisation of radioactive wastes in bitumen. Glasses for radioactive waste immobilisation. Vitrification technology. Long term durability of silicate glasses. Ceramic and metallic matrices. Nuclear waste transportation and storage. Nuclear waste disposal. Performance assessment.

12 N11 RADIATION SHIELDING This module gives an introduction to radiation shielding merging practical problems with industry standard transport codes in order to give a good understanding of the requirements for radiation shielding. The aims of this module are: To introduce the subject of radiation shielding and illustrate solutions to the particle transport equation in the context of Monte Carlo and deterministic transport codes. Simple shielding methods will be compared with sophisticated complex calculations in order to familiarise students with the essential concepts. As well as the core material, the course has four external lecturers who are experts in their respective fields. The use of Monte Carlo and Deterministic Codes will be presented in the context of industry needs and requirements. Shielding applications and the shielding design process will be discussed. On completion of this module, students should be able to: Demonstrate an understanding of the Particle Transport equation and the transport codes and methodologies used to solve it. Understand and be able to evaluate a shielding scenario using simple shielding methods. Demonstrate an understanding of the Monte Carlo and Deterministic methods and they are applied to radiation shielding calculations. Understand the systematic process that must be followed in order to design shielding to adequately protect those working with ionising radiation. Have an understanding of how the range of shielding solutions is consistent with common principles of radiation physics and radiological protection. This module, which will be delivered at the University of Liverpool, will include lectures on the following topics: The Particle Transport Equation Radiological protection principles Simple shielding methods Monte Carlo and Deterministic codes Advanced shielding methods The design process Real examples The module will have nine lectures, four of which will be presented by key experts from respective parts of the nuclear shielding community. The module has a practical component which allows experimental validation of the initial Monte Carlo simulation codes for neutron and gamma radiation fields. The post course assignment extends the simulation work to look at more advanced problems.

13 N12 REACTOR THERMAL HYDRAULICS This module describes the thermal hydraulic processes involved in the transfer of power from the core to secondary systems of nuclear power plants. Fundamental calculations associated with these processes will explained, examples set and results discussed. On completion, students should have obtained: An understanding of the heat transfer mechanisms in reactor systems. An understanding of fluid flow mechanisms in reactor systems. An appreciation of the limits on safe power removal from reactor cores. An appreciation of computer codes used to assess limiting power. An understanding of the influence of power conversion methods on reactor design. The ability to perform basic calculations of thermal hydraulic quantities in core channels. This module consists of a taught part (lectures) and an applied part. The taught part comprises: Introduction to Reactor Thermal Hydraulics. Heat transfer in fuel elements. Heat transfer by convection. Boiling heat transfer. Hydraulics of reactor system loops. Hydraulics of heated channels. Critical flows. Thermal hydraulic design. Steam and gas power cycles. For the second half of the module the student will be working on an assignment. This will be to produce calculations for the limiting thermal hydraulic quantities in the hot channel of a hypothetical reactor core. Results from an industry standard computer code (COBRA-EN, TRACPFQ) will be provided for comparison and comment.

14 N13 CRITICALITY SAFETY MANAGEMENT The N13 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. This module, recently updated to reflect the core competencies specified by the United Kingdom Working Party on Criticality (WPC), 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 a crash-course in the use of a Monte-Carlo code (i.e. MONK) for criticality safety analysis. The taught component is followed by a challenging 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 post-course assignment comprises 100% of the module assessment. & Assessment Upon completion of this module students should have a thorough grounding in the following topics: Criticality physics Methods of criticality control Criticality accidents and incidents Regulatory requirements and standards Criticality assessment methodology. Criticality hazards from plutonium, MOX and highly enriched fuels Criticality hazards during decommissioning, storage and transport Estimating sub-criticality Criticality codes and nuclear data Uncertainty and methods validation Criticality incident detection and response and be able to: Perform a comprehensive criticality safety assessment of an operational or (hypothetical) planned facility or plant, or part therein, involved in the use, storage, or processing of fissile materials which will require them to: Apply the appropriate regulatory legislation, guidance, or standards during this assessment Apply the range of techniques taught during the course (i.e. handbook curves & tables, analytical (hand) calculations, & computational methods) to assess the critical state, or the degree of sub-criticality, of facility or plant Justify their analysis through the appropriate use of data, benchmarks, crosscomparison of methods, and/or sensitivity analysis

15 N14 RISK MANAGEMENT The module introduces the concepts of risk management by reference to nuclear and other systems. An introduction is given to the mathematical analysis of risk based on probability modelling, and extended to the case of quality modelling. A case study based on the Chernobyl accident is presented. Comparisons of risk management across industries are presented, including engineering contracting, rail transport, chemical process and pharmaceuticals as well as nuclear. A strong feature of the module is the inclusion of industrial practitioners able to talk from direct experience. On completion, students should have obtained: A knowledge of systematic methods for identifying hazards An understanding of the mathematical concept of risk An appreciation of the techniques of probabilistic risk assessment Familiarity with examples of how such techniques may be used to understand and manage risk so as to satisfy the requirements of a regulator and of the general public. An appreciation of the new J-value technique for assessing health and safety expenditure. Introduction to risk concepts; nuclear plant example Identification and understanding of hazards Logistic and probabilistic descriptions of risk Quantifying failure: FMEA, Event trees, Fault trees Comparing risks and setting disparate risks in context Risk management in large industrial companies Probability modelling using distributions. Chernobyl Case study Strategies for managing nuclear risk Culture, ethics and public tolerability Introduction to the J-value method for assessing health and safety spend, particularly for averting radiation dose.

16 N21 Geological Disposal of Radioactive Wastes This module aims to explore the geoscience behind the disposal of radioactive wastes. Radioactive waste disposal has been a significant issue both historically and at present within the UK and this has resulted in major impacts to the nuclear industries both decommissioning and new-build. As a result of consultation it was decided that the UK s radioactive wastes will be disposed of via deep geological disposal in a candidate community and the UK is today moving towards deep geological disposal of its higher activity wastes using an approach based on voluntarism and partnership. Selection of a disposal site is subject to the site being geologically and hydrogeologically suitable and in a location that is not adversely vulnerable to geohazards. This module will examine historic and current UK developments in radioactive waste management and will introduce both geology and hydrogeology to the student. Shallow and deep methods of geological disposal and the multi-barrier concept will be investigated using UK and overseas case studies. Techniques of investigating the suitability of sites for geological disposal will be covered together with the correct recording methodology for soil and rock description. For both types of geological disposal the near and far-field processes will be considered; as will geohazards in relation to geological time. The module will examine the following: An introduction to geology and hydrogeology Radioactive waste disposal in the UK Regulation and legislation of radioactive waste disposal Geological methods of radioactive waste disposal including multi-barrier concepts Site investigation (including geophysical methods), soil and rock description Geohazards and the implications for geological disposal Case studies: historic and current methods both UK and overseas.

17 N23 RADIOLOGICAL ENVIRONMENTAL IMPACT ASSESSMENT The module aims to: Explain the purpose of radiological environmental impact assessment (REIA) and identify the circumstances in which theoretical (predictive) and measurementbased assessments are required. Understand the physical and chemical behaviour of radionuclides released into atmospheric and marine environments. Use state-of-the-art models effectively and intelligently to analyse the dispersion of radionuclides through the atmospheric, terrestrial and marine environments. Develop and apply dosimetric models to analyse the radiological impact of discharges on critical groups and the population as a whole by estimating individual and collective doses. Explain the special circumstances pertaining to C-14 and tritium (H-3) discharges and develop and apply specialist models to estimate the radiological impact of such emissions. Explain the methods used to measure environmental radiation and devise appropriate monitoring strategies for different types of discharge. Undertake a critical appraisal of actual radioactive discharges and associated impact assessments and undertake cost-benefit analyses for various discharge abatement proposals. Describe the UK regulatory framework pertaining to radioactive discharges and explain how international treaty obligations will impact on future regulatory requirements. Overview of REIA Requirements, Basic Concepts Atmospheric Dispersion Modelling Deposition Processes Exposure Pathways I Airborne and Deposited Activity Exposure Pathways II Foodstuffs Team-Based Assignment using PC-CREAM 08 Marine Dispersion Modelling Exposure Pathways III Marine Pathways Environmental Radiation Monitoring Laboratory-based Exercise Environmental Assay Radioactive Discharges in the UK a Perspective Regulatory Issues and International Perspectives

18 N29 DECOMMISSIONING TECHNOLOGY & ROBOTICS The aim of this module is to provide an ability to design and plan an effective decommissioning programme with an emphasis on immediate demolition using automation, robotics and remote handling techniques. Topics covered include strategies for effective decommissioning characterisation, costing and analysis, techniques for material cutting and waste minimisation, manual decommissioning techniques, human exposure and protection are included with elements of robotic systems and their integration and control. The module includes a look at the international picture and also an industrial site visit to Springfields in Preston (subject to security clearance). The coursework consists of the development of a decommissioning plan for a specific project. Course Worker radiation safety and shielding Characterisation of sites and the radioactivity present User interface design and implementation using LabView. Dismantling technology and cutting techniques minimising wastage. Dangerous radioactive species present in the decommissioning environment. Radiation effects on materials and electronics. Explosives in demolition. Examples of decommissioning projects. Robotics in a nuclear environment. Robotics design issues. Regulatory controls in nuclear decommissioning. Methods used for radiation detection and characterisation. International view of decommissioning

19 N30 THE DESIGN OF SAFETY-CRITICAL SYSTEMS This module provides students with knowledge of the design issues relevant to safety-critical systems. Topics included cover safety standards relevant to the design of engineering systems, and the IEC Safety Lifecycle and the implementation of the various steps of the process. Hazard identification and analysis techniques such as FMEA, HAZOP, and fault trees are also addressed. On completion of this module students should: Have an awareness of the IEC61508 Safety Lifecycle, functional safety, ALARP, and other standards; Understand the various hazard analysis techniques, including Failure Modes and Effects Criticality Analysis (FMECA), Fault Trees, Hazard and Operability Studies HAZOP including both quantitative and qualitative approaches Have an appreciation of the difference between random and systematic faults. and the overlap of this with software issues. Have an appreciation of the synergy between safety, reliability and quality. Safety standards relevant to the design of engineering systems. The IEC Safety Lifecycle and the implementation of the various steps of the process. Hazard identification and analysis techniques such as FMEA, HAZOP, Fault Trees etc. including the use of appropriate software tools. Qualitative and quantitative approaches. The hazard log. The assessment of risk and establishing safety criteria. Assigning SIL values. Random and systematic faults and the achievement of appropriate SIL values. The interplay between safety, reliability and quality.

20 N31 MANAGEMENT OF THE DECOMMISSIONING PROCESS It is absolutely necessary for clear and concise business cases to be made, for approval by the appropriate sanctioning authority, before nuclear decommissioning and radioactive waste management programmes of work are allowed to proceed. This module therefore sets out the framework for the production of such cogent cases including programme formulation, developing the programme with plans, making the most appropriate use of available funds and other resources, and arrangements for monitoring and controlling the work On completion, students should be able to: Expound business objectives, uses and sources of funds, the flow of funds, accounting terminology and key financial issues Carry out project financial and economic appraisals including capital investments Understand the importance of hazard reduction, project prioritisation, and Tolerability of Risk (ALARP) arguments Be fully conversant with modern planning processes including Work Breakdown Structures, Organisational Breakdown Structures, Responsibility Assignment, Activity Schedules, Cost Controls, Work Sequence Diagrams and Critical Path Analysis Understand and apply Earned Value reporting techniques Nuclear site licence, regulatory and site infrastructure costs Programme formulation and importance of waste routes The difference between the financial case and the wider economic, regulatory, resource, etc, issues Hazard reduction (including hazard and risk) Project prioritisation The planning framework (definitive list of liabilities, the liabilities estimate, liabilities reduction, optioneering and strategy development, the business case, concept/scheme/ detailed design, project initiation and Gateway Reviews Uses and sources of funds in the context of nuclear decommissioning The balance sheet, profit and loss account, and cash generation statement Financial and management accounting (including key accountancy concepts) Financial appraisal (payback, average annual rate of return, discounted cash flow Net Present Value and Internal Rate of Return) Programme and Project Planning, Work Breakdown Structures and Earned Value Reporting The module is underpinned with Case Studies and Worked Examples.

21 N32 EXPERIMENTAL REACTOR PHYSICS The module is based at the TRIGA low power research reactor facility of the Atomic Institute of the Austrian Universities in Vienna. Reactor neutronics and dynamics are demonstrated through experimental measurements of neutron fluxes, control rod calibrations, reactivity measurements and reactor power calibrations. An understanding and appreciation of the instrumentation and controls of a reactor are gained during the experiments and through hands-on operating experience at the reactor control panel. Safety aspects of reactor operation and fuel handling and inspection are emphasised. On completion of this module students will be able to: Demonstrate a full understanding of the principles underpinning reactor operations, control of operating conditions and management of safety Analyse and interpret data from reactor physics and dynamics measurements, leading to an assessment of the reactor condition. Determine by measurement the reactor properties such as neutron flux, control rod calibration, reactivity, and reactor power calibrations. Students will have experience in starting and operating a low-power reactor Prepare and deliver a presentations of the protocols used in the experimental measurement. This involves some analysis and organisation of data obtained in the reactor experiment, in order to draw conclusions about the reactor properties. Measurement of the thermal neutron flux density in the reactor core Measurement of the fast neutron flux in the reactor core centre Control rod calibration and determination of the core excess reactivity Calibration of the shim rod in the sub-critical region Reactivity and reactor period Determination of the reactivity value of uranium fuel- and graphite elements in different core positions Correlation function and void coefficient Measurement of the absorption cross-section with the danger coefficient method Measurement of the background radiation around the reactor at full power Reactor power calibration and determination of the temperature coefficient of the reactivity Criticality experiments Demonstration of a reactor pulse with different reactivity insertion Introduction to Reactor Instrumentation Demonstration of Compensated Ionisation Chamber and SPND Mock up Fuel Inspection Programme Unit template 1

22 N32 Part-Time EXPERIMENTAL REACTOR PHYSICS The module is held at the training rector VR-1 which is operated by Czech Technical University in Prague. The education and training within the module is oriented to the reactor physics, dosimetry, nuclear safety, and operation of nuclear reactor. The participants actively take part in all experiments, and independently evaluate acquired data. Principles of neutron detection, importance of delayed neutrons and their properties, reactor neutronics and dynamics are studied and demonstrated during various reactor experiments and measurements. An understanding of the reactor I&C and safety aspects of reactor operation are gained through hands-on reactor control. On completion of this module students will be able to: Demonstrate a full understanding of the basic phenomenon of reactor physics, behaviour of nuclear reactor and condition of its safety operation. Analyse and interpret data from reactor experiments and measurements. Set-up neutron detection system and use it for an in-core reactor measurement. Determine the reactor properties such as neutron flux, delayed neutrons properties, control rod calibration curve and reactivity. Analyse and explain the reactor behaviour at various operational states and conditions and the reactor response to various reactivity changes. Students will have experience in starting and operating a zero power reactor Evaluate the experimental results; prepare and deliver the protocols of the experimental measurements and present them. Adjustment the neutron detection system and determination its basic properties such as differential characteristics and dead-time. Measurement of the neutron flux in various positions of the reactor core. Determination of delayed neutrons properties and mass of fissionable material using delayed neutrons detection. Reactivity measurement by various methods (Source Jerk method, Rod Drop method, Positive period method, Source multiplication method) Control rod calibration by various methods (Inverse Rate method, Mutual Method). Study of the reactor behaviour in critical, supercritical and sub critical state with and without the external neutron source. Study of reactor responses to different reactivity changes (pulse, transient and frequency characteristics measurement). Analyses of temperature effects in reactor and their influence on behaviour and operation of nuclear reactor; determination of reactor void coefficient Critical experiment safety approaching the critical state. Start-up and operation of VR-1 reactor by students.