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THE WORLD NUCLEAR UNIVERSITY With support from NUCLEAR WORKFORCE DEVELOPMENT Presents a comprehensive curriculum for

WNU Nuclear Training by PM DIMENSIONS

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Comprehensive training on various aspects of nuclear engineering conducted by WNU and PM DIMENSIONS, especially for developing markets

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Page 1: WNU Nuclear Training by PM DIMENSIONS

THE WORLD NUCLEAR UNivERsiTyWith support from

NUCLEAR WORkfORCE DEvELOpmENT

Presents a comprehensive curriculum for

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2 | Nuclear Workforce Development

PrePare your EmpLOyEEs for GROWTH iN the Nuclear iNDustry

Contents

about World Nuclear university 2

foreword 3

Projections of Manpower and educational Need 5

the Value of WNu Programmes 6

range of available topics 7

WNu Programmes at a Glance 8

Programme Details 9 - 46

inaugurated in 2003, the WNu is a partnership built on four “founding supporters”: the international atomic energy agency (iaea), the oecD’s Nuclear energy agency (oecD/Nea), the World Nuclear association (WNa) and the World association of Nuclear operators (WaNo). the WNu partnership also encompasses key institutions of nuclear learning in more than 30 nations.

the mission of the World Nuclear university partnership is to enhance international education and leadership in the peaceful applications of nuclear science and technology.

chartered as a non-profit corporation, the WNu pursues this mission through programmes organized by the WNu coordinating centre (WNucc) in london. relying on administrative support from WNa, the WNucc oversees activities designed to harness the strengths of partnership members in pursuit of shared purposes.

about WORLD NUCLEAR UNivERsiTy

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fOREWORD

the expanding worldwide commitment to nuclear power as an essential clean-energy technology for the 21st century has given rise to two crucial needs: (1) capable and visionary leadership in the nuclear world; and (2) a substantially enlarged global workforce of knowledgeable and skilled nuclear professionals. the WNu partnership has focussed on both goals.

the WNu flagship is the WNu summer institute, held at oxford university each July-august. this six-week course is designed to expand the horizons, and to inspire, mid-level nuclear professionals who have been identified by their organizations as possessing the potential to become senior leaders in the nuclear world. there are now more than 700 former WNu fellows at work – and advancing – in nuclear organizations in more than 40 countries.

building on the success of the summer institute, the WNu has now focussed on workforce development. Many of these WNu initiatives are encompassed in the educational opportunities described in this brochure.

We are proud to offer here a wide range of high-quality short-term training programmes designed to assist nuclear organizations in building the capable workforce teams they will need as participants in an expanding and fast-globalizing nuclear industry. We look forward to delivering these courses with confidence in the future of nuclear power and with pride in contributing to the expansion of a skilled worldwidenuclear profession.

John ritchPresident

World Nuclear university

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the WNU iN ACTiON:beiJiNG aND oxforD

the one-week WNu "Key issues" orientation course in beijing

the six-week WNu summer institute at oxford university

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Worldwide nuclear generation capacity today totals about 370 GW.

the iaea and the World Nuclear association both project that global nuclear generating capacity could grow by as much as 180 GW in the next decade and by another 250 GW by 2030. today more than 60 reactors are under construction worldwide. even "low growth" estimates from iaea and WNa foresee a dramatic nuclear expansion.

Worldwide nuclear new-build at this expansive rate will require a corresponding increase in the nuclear industry's professional workforce.

but important trends point in exactly the opposite direction. about 50% of today's global nuclear workforce is set to retire in the next 10 years, and studies by the iaea and national industry associations project a widening gap between need and availability of professionals skilled in nuclear engineering, operations, maintenance and radiation protection.

this gap must be closed by high-quality training in all aspects of nuclear generation and the nuclear fuel cycle.

ProJectioNs of mANpOWER AND EDUCATiONAL NEED

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WNu programmes cover all aspects of: (1) nuclear science and technology; and (2) nuclear power projects. they are:

t Presented by experienced industry experts.

t Designed to facilitate both understanding and application.

t Well-paced, providing for comprehension followed by discussion.

t Delivered in an easy-to-understand format using examples and case studies.

t available in introductory and advanced level programmes.

the vALUE of WNU ProGraMMes

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the WNu curriculum for Nuclear Workforce Development is designed to support established nuclear organizations and new entrants in training their employees across a range of topics spanning the entire nuclear supply chain. Drawing strength from the educational experience of PM Dimensions, the curriculum covers science, technology and management.

PURPOSEWNu courses:

u equip participants with requisite knowledge in their chosen area

u enable practical applications

u set a base for further study and research

LEVELSWNu programmes are offered at:

Introductory level

Advanced level

NUCLEAR TOPICSProgrammes cover these nuclear topics:

u Design and engineering

u Radiation safety

u Environmental management

u Operational safety

u Maintenance

u Risk management

u Accident management

u Quality management

u Decommissioning

raNGe of AvAiLABLE TOpiCs

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WNu ProGraMMes AT A GLANCE

title DuratioN

(1) ORiENTATiON pROGRAmmEsNuclear Power today 1 day

Key issues in the World Nuclear industry today 1 week

(2) NUCLEAR ENGLisH COURsEsstandard introductory course 3 days

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(3) WORkfORCE DEvELOpmENT ProGraMMes

coDe title leVel DuratioN

ENGiNEERiNG DEsiGN (ED)

ED01 introduction to nuclear reactors and reactor theory introductory 5 days

ED02 Nuclear power plant engineering advanced 5 days

ED03 Nuclear reactor thermal hydraulics advanced 5 days

ED04 advanced programme on turbine generators advanced 3 days

ED05 Mechanical components and equipment for NPPWW introductory 5 days

RADiATiON sAfETy (Rs)

Rs01 radiation protection in nuclear power plants advanced 5 days

Rs02 radiation protection and safety in medical applications of ionizing radiation

advanced 5 days

Rs03 radiation protection and safety in industrial applications of ionizing radiation

advanced 5 days

ENviRONmENT mANAGEmENT (Em)

Em01 environmental impact of nuclear power plants introductory 3 days

NUCLEAR sAfETy (Ns)

Ns01 introduction to nuclear safety introductory 5 days

Ns02 Deterministic safety analysis of nuclear power plants advanced 5 days

OpERATiONs & mAiNTENANCE (Om)

Om01 reliability centred maintenance introductory 3 days

Om02 efficient and safe operation of nuclear power plants introductory 3 days

QUALiTy mANAGEmENT (Qm)

Qm01 Quality assurance for nuclear power plants introductory 3 days

Risk mANAGEmENT (Rm)

Rm01 Probabilistic safety assessment advanced 5 days

DisAsTER mANAGEmENT (Dm)

Dm01 emergency preparedness and response advanced 5 days

DECOmmissiONiNG (DE)

DE01 Decommissioning of nuclear power plants introductory 3 days

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Nuclear Power today

the prime aim of this intensive course is to equip participants with a sound understanding of the key issues underlying the development of nuclear power today, together with an appreciation of its likely expansive future. for those already with knowledge of some aspects of nuclear, it will broaden their horizons to the full range of issues that underlie it. for others newer to the field, it should open up many of the apparent mysteries and possible misunderstandings. the course is intentionally international in focus, based on WNu’s experience of running longer courses both in the uK and overseas countries.

the format is for 10 half-hour units, each consisting of 15-20 minutes of presentation, followed by questions and class discussion. it is expected that groups will be no larger than 20.

WhO ShOULD ATTEND?

People who would benefit from this course include any in nuclear companies seeking broader knowledge of the entire business, particularly new hires, staff in companies new to the nuclear sector and financial sector executives needing to gain detailed nuclear knowledge.

DURATION: 1 DAy

Orientation programmes

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these events are designed to enhance the knowledge of how nuclear science and technology are applied in the world today, while encouraging an expansive view of where it is likely to go in the future. international experts lecture on a wide range of topics with the aim of offering practical knowledge, a global perspective and an exciting vision of the future, which should stimulate interest amongst attendees in pursuing further careers in this area.

the overall aim of the course is to give attendees a comprehensive knowledge of the key issues in the world industry today, to enable them to place their own current role into perspective while also opening their eyes to the opportunities of the future. a related objective is to encourage different groups involved in nuclear within the country to communicate more closely with each other, to the benefit of all.

each course aims at attracting upwards of 70 attendees and 17 had been held up to the end of 2010, in developing nuclear countries such as argentina, brazil, china, Korea and south africa. the course is flexible and can be shortened to 3 days or adapted to local requirements.

WhO ShOULD ATTEND?

Participants may be masters-level university students in nuclear science and engineering, staff at nuclear research centres, professionals in the local nuclear industry and equivalent government employees, including regulators and energy planners.

Key issues in the World Nuclear industry today

DURATION: 1 WEEk

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Nuclear english courses

in today’s globalizing nuclear industry, proficiency in english is an essential asset for nuclear professionals. WNu’s intensive english-language courses help learners prepare for the english-speaking environment, enabling day-to-day communication with colleagues, the writing of effective reports, and participation at conferences.

People should be motivated to learn english in a nuclear-specific context alongside fellow professionals from other countries. by attending the course, participants will be aiming to improve fluency, accuracy, and range of terminology, rather than mastering the basic aspects of the english language.

Programmes feature a range of activities tailored to suit participants’ needs. in particular, there will be opportunities for simulated practice of situations typically encountered in professional life, such as meetings, presentations and interactions with the public. the textbook Nuclear english (WNu Press) provides an important reference throughout the course.

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ED01introduction to Nuclear reactors and reactor theory

the nuclear reactor forms the heart of a Nuclear Power Plant (NPP). fundamental to a nuclear reactor are the subjects of nuclear physics and reactor physics which deal with the basic aspects of the physics design of nuclear reactors. this knowledge is essential for understanding the reactor behaviour during, both, normal operation as well as abnormal conditions. this programme is an introduction to the basics of nuclear reactors and deals with the fundamental aspects of physics related to them. the topics covered in this programme include: reactor criticality, design, dynamics, control and safety. an introduction to different types of reactors is also given. the various safety systems used in NPPs and the significance attached to safety are explained.

MODULES

u Nuclear physics – fundamentals, nuclear structure

u radioactive decay

u fission and fusion processes, nuclear cross sections

u interaction of particles and ionizing radiations with matter

u Nuclear reactor systems and components

u functions of the various reactor systems

u fuel, moderator and coolant

u typical reactor control system

u Neutronics and reactor criticality

u steady state and dynamic behaviour of reactors

u Various types of reactors

u components and systems of an NPP

u Nuclear reactor safety and safety systems

DURATION: 5 DAyS LEVEL : INTRODUCTORy

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Engineering Design

ATTENDEES WILL LEARN AbOUT

u fundamentals of nuclear physics, fission, fusion processes

u the basics of the physics of nuclear reactors

u Nuclear reactor criticality and simple methods of criticality calculations

u Nuclear reactor components and systems

u Nuclear reactor control and dynamics

u Different types of reactors

u Various components and systems of an NPP

u importance of safety and various safety systems in NPPs

WhO ShOULD ATTEND?

u organizations planning to enter the nuclear sector

u organizations interested in refreshing their knowledge of nuclear reactors

u consultants attached to the nuclear industry

u Non-nuclear organizations that wish to broaden their knowledge

u Government representatives from the environment and energy departments

u representatives from the energy and environment departments of organizations

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DURATION: 5 DAyS LEVEL: ADVANCED

ED02Nuclear Power Plant engineering

an NPP has a large number of systems and components, including those essential for their operation, control and safety. their proper functioning is a must for carrying on the normal operation and ensuring the safety of an NPP. it is necessary for every practicing nuclear engineering professional to be well acquainted with such systems used in various reactors. such systems shall be dealt with in detail in this programme. this programme also deals with the reactor design aspects, inclusive of the safety analysis and assessment. the reactor behaviour under various conditions, such as, normal operation as well as transient and accident conditions is to be explained. the secondary system and the various auxiliary systems of the NPP will be also dealt with.

MODULES

u conceptual design of NPPs

u types of NPPs and comparison of key parameters

u influence of reactor design on power conversion system

u reactor core design, components and materials

u reactor fuel design and materials

u reactor coolant system (rcs) and components

u secondary coolant system and balance of Plant (boP)

u reactor control and protection systems

u steady state and dynamic behaviour of NPPs

u reactor auxiliary systems

u introduction to reactor safety

u safety systems for NPPs

u reactor auxiliary systemsDEES WILL LEARN AbOUT

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u the different types of NPPs and their systems and components

u the basic design aspects of different types of NPPs, the functional aspects of different systems required for ensuring safety under normal operation as well as under different abnormal conditions, including postulated accident scenarios

u the process systems, secondary system and the various auxiliary systems of NPPs

u the reactor system behaviour under various states such as normal operation, transient and accident conditions

u how to assess the various designs of NPPs and carry out basic design studies of proposed reactor systems

u the basics of reactor system dynamics, safety and safety assessment

WhO ShOULD ATTEND?

u senior managers/engineers in organizations planning to enter the nuclear sector

u organizations interested in advancing their knowledge of NPPs

u consultants attached to the design of systems and equipment for NPPs

u Nuclear equipment manufacturers and suppliers

u consultants engaged in Qa of nuclear equipment and systems

u Government representatives from the environment and energy departments

u representatives from the energy and environment departments of organizations

REQUISITE QUALIFICATION

this is an advanced programme. therefore, to benefit from the programme, the participants should have a bachelor’s degree in science/engineering and basic knowledge of nuclear physics, reactors, engineering equipment etc. it will be advantageous to attend the programme ‘eD01: introduction to Nuclear reactors and reactor theory’ before attending this programme, though it is not a must.

Engineering Design

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DURATION: 5 DAyS LEVEL: ADVANCED

ED03Nuclear reactor thermal hydraulics

Knowledge and application of the science of heat transfer and fluid flow, i.e., thermal hydraulics, as applied to nuclear reactors, is required to ensure effective heat removal under all conditions. the heat generated in a nuclear reactor should be removed effectively while maintaining the various temperatures (e.g., coolant, cladding, etc.) within specified limits, to ensure safety. the geometries as well as the phenomena encountered in nuclear reactors are very complex and the programme deals with various facets of this issue such as conduction, convection as well as radiation heat transfer (depending on the conditions) in nuclear fuels, thermal hydraulics of reactor coolant system and other systems. the topics of sub-channel analysis and hot-spot and hot-channel factors are introduced to account for the complex geometry and deviations from the nominal conditions. the phenomena of two phase flow and heat transfer, important from the point of view of accident analysis, are also covered in this programme.

MODULES

u introduction to nuclear reactors

u heat generation in nuclear reactors

u thermal hydraulic characteristics of power reactors

u safe energy removal from the reactor core

u introduction to heat transfer and fluid flow mechanisms

u thermal hydraulics of reactor fuel channels

u conduction heat transfer in fuels of different geometries

u convective heat transfer

u forced convection heat transfer

u thermally induced flow and heat transfer

u radiation heat transfer

u hot-spot and hot-channel factors

u sub-channel analysis of fuel channels with rod bundles

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u hydraulics of reactor system loops and heated channels

u Pressure drop and pumping power calculations

u Parallel channel flow

u two-phase flow and heat transfer

u influence of thermal hydraulics on reactor design parameters

u application of thermal hydraulic principles to design and analysis of nuclear reactors

ATTENDEES WILL LEARN AbOUT

u the various thermal hydraulic phenomena relevant to nuclear reactors

u the analysis of simple geometries of fuel channels and various temperatures such as coolant temperature, cladding temperature, etc.

u the basics of forced convection and thermally induced flows in reactor systems

u the application of special techniques of analysis such as sub-channel analysis and hot-spot and hot-channel analysis to fuel design

u the analysis of pressure drop and pumping power requirements in reactor loops

u the application of basic thermal hydraulic principles to the design and analysis of nuclear reactors

WhO ShOULD ATTEND?

u organizations interested in advancing their knowledge of thermal hydraulics of nuclear reactors

u consultants involved in thermal hydraulic design and analysis of systems and equipment for NPPs

u Nuclear thermal equipment designers and manufacturers

u Governmental representatives from environmental and energy related departments

u organizations involved in energy and environmental work

u senior managers/engineers from organizations planning to enter the nuclear sector

REQUISITE QUALIFICATION

this is an advanced programme. therefore, to benefit from it, the participants should have a bachelor’s degree in science/engineering and basic knowledge of heat transfer and fluid flow.

Engineering Design

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DURATION: 3 DAyS LEVEL: ADVANCED

ED04advanced Programme on turbine Generators

the role of a steam turbine-Generator (t/G) is pivotal in converting fission energy into electrical energy, and delivering it to the power grid. appropriate functioning of the turbine is essential for the overall safety of the NPP. for it, the operation and maintenance staff of an NPP should have adequate knowledge of the t/G system, along with its control systems, operation and maintenance procedures, procurement and replacement of parts, when required, and so on. this programme aims at imparting in-depth information about the t/G, its proper operation, maintenance and inspection. Problems related to corrosion, erosion, vibration, etc., and their solutions are discussed. ageing related problems and their solutions are also dealt with. case studies are also presented for the benefit of the participants.

MODULES

u brief introduction to t/G system and its components

u Description of turbine control system including speed governor, speed load changer, steam pressure regulator, over speed trip device, vacuum trip devices, low speed switches

u Monitoring and trending of turbine parameters

u t/G oil system monitoring, trending and maintenance

u inspection and maintenance of the steam turbine and its parts such as stop valves, control valves, bleeder trip valves, spill valves, bypass valves, t/G bearings, and turbine rotors

u Problems caused by moisture such as blade erosion, diaphragm erosion, casing erosion and their resolutions

u flow assisted corrosion of turbine parts like bleeder trip valves, spill valves, extraction pipe, condensate pipe and steam trap lines

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u reasons for turbine generating power lesser than that rated and the measures to rectify the problem

u causes of t/G vibration and solution of the problem; discussion of related case studies

u replacement of turbine parts, including procurement and quality assurance

u Main condenser inspection and maintenance

u tube leak checking, air leakage checks, hydro test

u ageing related issues of turbine parts such as rotor blades, diaphragms, couplings, bearings, steam seals and control system expansion bellows

u ageing related issues of turbine auxiliaries such as oil pumps, condensate pumps, circulating water pumps, main condenser, heater, extraction lines and the like

ATTENDEES WILL LEARN AbOUT

u t/G details

u Details of turbine control system and turbine oil system

u Monitoring and trending of turbine and turbine oil system parameters

u inspection, maintenance of turbine and its parts

u erosion/corrosion of turbine parts; solutions to the problem

u operation, maintenance, inspection of turbine, related problems and solutions

u turbine under performance, reasons and solutions

u Vibration of turbine/generator and solution of the problem

u issues associated with the ageing of t/G and its components, and their solutions

WhO ShOULD ATTEND?

u Power plant engineers

u supervisors and senior technicians involved in the operation and maintenance of power plants

u Personnel from the inspection and planning department of power plants

u organizations (ePc, utility companies) planning to enter the nuclear energy sector

u engineering design consultants and technical service providers associated with the nuclear sector

u organizations engaged in the design and manufacture of t/G equipment and auxiliaries

u environmental protection agencies

u Government representatives dealing with the energy sector

u staff of regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. therefore, the participant should have a degree/diploma in engineering. experience in power plant operation and maintenance will be useful.

Engineering Design

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DURATION: 5 DAyS LEVEL: bASIC

ED05Mechanical components and equipment for Nuclear Power Plants

efficient functioning of the large variety of mechanical equipment used in NPPs is essential for the safe operation of the plant. the Pressurized heavy Water reactor (PhWr) equipment and components differ in many respects from PWr. this programme is designed to provide a comprehensive overview of the mechanical equipment and components used in different NPPs. the design, construction/installation, working principle, operation and maintenance, inspection and safety aspects will be explained at length. the specifications prescribed by codes, standards and other design aspects laid down by regulatory body will also be discussed in detail.

MODULES

u introduction to components and equipment used in NPPs

u reactor pressure vessel and internals

u calandria vessel in PhWrs

u reactor vessel penetrations and nozzles

u reactor shielding

u reactor coolant channels in PhWrs

u Primary coolant system including pumps

u fuel handling system

u steam generator

u Pressurizer/pressurizing system

u equipment in safety systems

u Mechanical equipment in the balance of plant

u Valves, pumps, pipes, tubes, sealing devices, compressor, vacuum pumps, bearings, etc.

u Ventilation system

u turbine, condenser, feed heater

u life assessment and maintenance management

u codes, standards and specifications

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ATTENDEES WILL LEARN AbOUT

u Mechanical equipment used in different types of NPPs

u classification of mechanical equipment on the basis of the operating principles

u basic design aspects of mechanical equipment used in NPPs

u construction and installation aspects

u Probable challenges during installation

u operational and maintenance challenges and their troubleshooting

u life assessment and maintenance management of equipment

u applicable codes, standards and specifications for equipment of all types

WhO ShOULD ATTEND?

u organizations (ePc, utility companies) planning to enter the nuclear sector

u engineering design consultants and technical service providers in the nuclear sector

u organizations engaged in the design and manufacture of equipment

u environmental protection agencies

u Government representatives dealing with the energy sector

u regulatory bodies

REQUISITE QUALIFICATION

this is an introductory programme. therefore, to benefit from it, it will be useful if the participant holds a degree/diploma in engineering.

Engineering Design

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DURATION: 5 DAyS LEVEL: ADVANCED

RS01radiation Protection in Nuclear Power Plants

the process of fission in a nuclear reactor generates a large amount of radioactivity and radioactive materials. it is, therefore, essential to ensure adequate radiation protection, particularly to workers in the plant. thus, radiation monitoring and assuring radiation protection is an important aspect of safety. this programme deals with the various facets of the radiation protection programme in an NPP. the radioactive releases from NPPs, their hazards and biological effects are discussed. Details of radiation monitoring and measurement, protective equipment and radiation protection of personnel are dealt with. issues such as internal and external contamination, emergency preparedness, and regulatory limits are also discussed.

MODULES

u Natural and man-made radiation sources

u interaction radiation with matter

u radiation units

u radiation hazards

u the biological and genetic effects of radiation

u Quantification of the effects of radiation on the human species

u radioactive releases from NPPs during normal operation and under abnormal and accident conditions

u standards of radiation protection

u Protection of workers against radiation exposure

u Personnel protection equipment

u standards for the intake of radionuclides

u computation of exposure, dose, field, manrem, etc.

u Manrem budgeting and control

u radiation measurement

u instruments for measuring radiation

u radiation monitoring and surveillance

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u Measurement of the dose received by radiation workers

u radiation emergency preparedness and handling of radiation emergencies

u surface and internal contamination and control

u regulatory limits

u safety culture

ATTENDEES WILL LEARN AbOUT

u radiation hazards and the biological effects of radiation

u radiation units and measurement

u radiological releases and standards of radiation protection

u radiation monitoring and surveillance

u radiation dose, manrem budgeting and control

u handling radiation emergencies

u contamination control

u regulatory issues

WhO ShOULD ATTEND?

u Personnel engaged in radiation protection activities

u employees of NPPs

u organizations owning and operating NPP

u radiation protection equipment designers and manufacturers

u radiation protection equipment suppliers

u People interested in advancing knowledge of radiation protection and safety in NPPs

u representatives of government departments designated for the implementation of radiation safety

u staff interested in advancing their knowledge of radiation protection and safety in NPPs

u staff of regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. to benefit from the programme, the participant should have a degree in science or a degree/diploma in engineering. basic knowledge of radiation and radioactivity will be useful.

Radiation Safety

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DURATION: 5 DAyS LEVEL: ADVANCED

RS02radiation Protection and safety in Medical applications of ionizing radiation

ionizing radiation is being used extensively in human healthcare programmes. Diagnostic radiology facilities using equipment incorporating x-ray generators, such as general radiography and fluoroscopy units, ct scanners, interventional radiography, mammography units, dental x-ray units, etc., are extensively used worldwide. While ionizing radiations play a significant and indispensable role in the diagnosis and treatment of cancer, it may be harmful to the workers and general public, if used without due caution and care. this programme deals with the various aspects of the use of ionizing radiation for medical applications. safety in the handling of equipment and safe disposal of the wastes is particularly emphasized. the regulatory aspects are also dealt with.

MODULES

u basic radiation physics

u interaction of radiation with matter

u radiation quantities and units

u biological effects of radiation

u operational limits

u radiation detection and measurement

u radiation protection in:

w x-ray diagnostic radiology, including fluoroscopy, ct, mammography, dental x-ray and interventional radiography

w radiation therapy, including cobalt therapy, high-energy beam therapy and brachytherapy

w Nuclear medicine – diagnostic and therapeutic

u radiation hazard evaluation in:

w x-ray diagnostic radiology

w radiation therapy

w Nuclear medicine

u Disposal of radioactive waste

u transport of radioactive material

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u radiation accidents, case studies and lessons learned

u regulatory aspects of medical applications of ionizing radiation

u emergency response plans and preparedness

ATTENDEES WILL LEARN AbOUT

u Different types of equipment used in diagnostic radiology, interventional radiology, computerized tomography (ct), mammography and radiotherapy

u radiation protection and safety aspects in the handling of medical equipment

u regulatory aspects to be complied with

u use of radiation monitoring instruments

u Measurement of radiation levels around medical equipment and in controlled areas

u type approval procedures for medical equipment

u Physical security and radiation safety in using medical equipment

u Physical security during transport, storage and decommissioning

u safe disposal of radioactive waste

u causes and avoidance of potential exposure

u best practices and safety culture

WhO ShOULD ATTEND?

u staff engaged in handling and using medical radiation equipment

u senior level representatives from organizations manufacturing equipment for medical applications of ionizing radiation

u Medical equipment suppliers

u organizations interested in advancing their knowledge of radiation protection and safety in the medical applications of ionizing radiations

u Government representatives responsible for the implementation of radiation protection programmes in different radiation facilities for medical uses

REQUISITE QUALIFICATION

this is an advanced programme. to benefit from the programme, the participant should have a degree in science or a degree/diploma in engineering.

Radiation Safety

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DURATION: 5 DAyS LEVEL: ADVANCED

RS03radiation Protection and safety in industrial applications of ionizing radiation

there has been a significant increase in the industrial applications of radiation sources globally and, as a result, the number of workers in this field is steadily increasing. efficacy of radiation and radio-isotopes in promoting industrial growth without compromising safety and quality of the end product has been well established. ionizing radiation gauging devices (nucleonic gauges) are used for online industrial process control of parameters. radiography is one of the important Non-Destructive testing (NDt) techniques for ensuring integrity of equipment and structures such as vessels, pipes, welded joints, castings, etc. use of high intensity and highly penetrating ionizing radiations for the sterilization of healthcare products is perhaps one of the most beneficial applications.. radiation doses required to achieve the desired effect range from tens of Gy to several kGy. since these radiation doses are detrimental to human health, utmost care needs to be taken during the operation of these facilities. supervising and operating personnel in such facilities must possess in-depth knowledge of radiation safety, including the design and operational aspects of the equipment and facility. this programme deals with various aspects of the use of ionizing radiation for industrial applications. the challenges associated with industrial occupational radiation protection, due to the large variety of work site conditions encountered, are addressed. strong emphasis on worker training and consistency of operation (seeking best practices) for improved radiation protection is given. Particular emphasis is given to safety in handling and use of the equipment and safe disposal of the radioactive wastes. the regulatory aspects are also dealt with.

MODULES

u basic radiation physics

u interaction of radiation with matter

u radiation quantities and units

u biological effects of radiation

u operational limits

u radiation detection and measurement

u radiation protection in:

w the use of ionizing radiation gauging devices and well logging

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w industrial radiography, Non-Destructive testing (NDt)

w Gamma irradiation chambers

w radiation processing facilities for the sterilization of medical products, food and allied products, cross-linking of wires and cables, vulcanization of rubber, wood-polymer composites, etc.

u radiation hazard evaluation & control in:

w the use of ionizing radiation gauging devices

w industrial gamma and x-ray radiography

w Gamma irradiation chambers

w high intensity electron, x- and gamma-ray radiation processing facilities

u Disposal of radioactive waste

u transport of radioactive materials

u radiation accidents, case studies and lessons learned

u regulatory aspects of industrial applications of ionizing radiation

u emergency response plans and preparedness

ATTENDEES WILL LEARN AbOUT

u Different types of equipment used in nucleonic gauges, well logging, industrial radiography and radiation processing facilities

u radiation protection and safety aspects in handling industrial equipment

u regulatory aspects to be complied with

u use of radiation monitoring instruments

u Measuring radiation levels around industrial equipment and in controlled areas

u radiation dosimetry for radiation processing of products

u type approval procedures for industrial equipment

u Physical security in using industrial equipment

u Physical security during transport, storage and decommissioning

u safe disposal of radioactive wastes

u causes and avoidance of potential exposures

u built-in safety systems in radiation processing facilities

u effective operational safety in radiation processing facilities

u best practices and safety culture

WhO ShOULD ATTEND?

u Personnel engaged in handling and using industrial radiation equipment

u senior managers / engineers of organizations dealing with manufacture of equipment for industrial applications

u industrial equipment suppliers

u Government employees in radiation protection departments responsible for the implementation of radiation protection programme in different radiation facilities for industrial uses

u regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. to benefit from the programme, the participants should have a degree in science or a degree/diploma in engineering.

Radiation Safety

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EM01environmental impact of Nuclear Power Plants

as a source of electrical energy, NPPs offer a special advantage in that they do not release any conventional pollutants into the environment. the main release of concern is radioactivity. this programme deals with the types of releases from an NPP and the steps taken to protect the environment. the activities in this regard start soon after site selection and continue through plant construction, operation and finally decommissioning and waste disposal. the environmental protection and surveillance activities are discussed in detail. the biological effects of radiation, dose assessment are explained. Various legislative and regulatory criteria related to environmental protection, environmental decision making processes and assessment of public perception are discussed at length.

MODULES

u introduction to environment

w Physical environment

w biological environment

u Need for environmental protection

u environmental releases from NPPs

u Dispersion through air

w General meteorology

w site specific data

w atmospheric modelling

w unusual site conditions

u Dispersion through surface water

w hydrological features

w site specific data

w hydrological modelling

u Dispersion through sub-surface water

w Ground water characteristics

w hydrological investigations

w site specific studies

u environmental surveillance

w environmental monitoring programme

w Pre-operational phase

w environmental monitoring for operational phase

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Environment Management

u biological effects of radiation

u assessment of radiation dose

u land and water use

u Process of environmental decision making

u Public perception and its impact on environmental decision making

u legislative and regulatory criteria for environmental protection

ATTENDEES WILL LEARN AbOUT

u Why environmental protection is of great concern today

u environmental releases from NPPs

u Dispersion through air, surface water and sub-surface water

u hydrological modelling

u Generation of site specific data

u environmental surveillance during various phases

u biological effects of radiation and assessment of dose

u Public perception and environmental decision making

u legislative and regulatory criteria

WhO ShOULD ATTEND?

u agencies involved in environmental assessment

u Government bodies involved in environment protection activities

u Government bodies dealing with the energy sector

u representatives of regulatory bodies

u organizations engaged in the design and manufacture of environmental protection equipment

u organizations engaged in the design and manufacture of radiation measuring instruments and radiation protection equipment

u engineering design consultants and technical service providers associated with the nuclear sector

u organizations (ePc, utility companies) planning to enter the nuclear sector

REQUISITE QUALIFICATION

this is an introductory programme for understanding the environmental impact of NPPs. to get optimum benefit from the programme, knowledge of radiation and its effects will be useful. the minimum qualification of the participants for attending the programme is a bachelor’s degree in science/engineering.

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NS01introduction to Nuclear safety

the main objective of nuclear safety is the radiation safety objective, which calls for compliance with the internationally accepted stipulations on radiation protection. this is achieved by implementing the technical safety objective, which requires meeting the safety requirements in various phases of the plant as well provision of adequate accident mitigation and management measures. this programme is designed as an introduction to the various issues relevant to assuring the safety of an NPP. the importance given to safety during the various phases of the plant is explained. the various systems provided and their functions are discussed. the classification of the plant system, structures and components (sscs) based on their safety significance is dealt with. the methodology of safety analysis, various nuclear safety criteria laid down by the regulatory bodies are also explained. the environmental impact of NPPs, issues such as emergency preparedness and response, and governmental organizations are discussed.

MODULES

u introduction to nuclear reactors

u conceptual design of NPPs

u importance given to safety in NPPs – safety objectives and defence in depth

u safety considerations in various phases of the NPP, viz., siting, design, construction, operation, decommissioning, etc.

u structures, systems and components (sscs) important to safety and their classification

u engineered safety features (esfs) and their functions

u initiating events, Design basis accidents (Dbas), beyond Design basis accidents (bDbas)

u accident analysis and safety assessment

u accident prevention / accident management

u inventory and localization of radioactive materials in the plant

u radiation protection and acceptance criteria

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Nuclear Safety

u Dispersion and health consequences of radioactive releases

u environmental impact of NPPs

u Management responsibilities

u Governmental infrastructure for ensuring safety

u importance of quality assurance

u emergency preparedness and response

ATTENDEES WILL LEARN AbOUT

u Nuclear reactor systems and the internationally defined safety objectives for them

u importance given to safety in a nuclear power plant and the means and procedures for ensuring safety throughout the life of the plant and its subsequent decommissioning

u classification of plant systems, structures and components based on their safety significance

u initiating events, Dbas and bDbas

u radiological hazards in the plant and the radiation protection measures

u Dispersion of radioactive materials and their health consequences

u implementation of safety measures at nuclear power plants

u safety analysis approaches

u accident prevention and management measures

u emergency preparedness and response

WhO ShOULD ATTEND?

u organizations (ePc, utility companies) planning to enter the nuclear sector

u engineering design consultants and technical service providers in the nuclear sector

u organizations engaged in the design and manufacture of equipment for NPPs

u organizations involved in the construction and operation of NPPs

u employees of operating NPPsu environment protection agenciesu Government agencies dealing with

the energy sectoru regulatory bodies

REQUISITE QUALIFICATION

this is an introductory programme for understanding the concept of nuclear safety. to get optimum benefit from the programme, knowledge of nuclear reactor theory and plant engineering will be useful. the minimum qualification required for the participants is a bachelor’s degree in science/engineering.

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NS02Deterministic safety analysis of Nuclear Power Plants

safety analysis forms a major part of the design and licensing process for nuclear power plants. safety analysis is carried out to ensure that the various provisions for safety are adequate to maintain the plant parameters within acceptable limits under various postulated conditions including normal operation, anticipated operational occurrences and accidents.

this programme on ‘Deterministic safety analysis of Nuclear Power Plants’ introduces the different approaches to safety analysis, postulated initiating events and their categorization. the two approaches of deterministic safety analysis, viz., conservative deterministic safety analysis and the best estimate Plus uncertainty (bePu) analysis are explained. consideration of the non-availability of systems and components (e.g. single failure criterion) and the effects of nodalization and plant modelling (user effects) are dealt with. the computer codes for loca analysis and their verification and validation are discussed. the application of Dsa to safety analysis of NPPs and the regulatory review of Dsa are also dealt with.

MODULESu introduction to safety analysis

w Deterministic and probabilistic safety analyses

u Different plant states of NPPs and Postulated initiating events (Pies)

w Grouping of Pies – anticipated operational occurrences (aoos), Design basis accidents (Dbas), beyond Design basis accidents (bDbas)/severe accidents (sas)

w acceptance criteria for different categories of Pies

u conservative Deterministic safety analysis (Dsa)

w credit for operator action on conservative basis

u best estimate Plus uncertainty (bePu) analysis

w Why best estimate (be) approach

w sensitivity analysis and uncertainty analysis

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Nuclear Safety

u initial and boundary conditions

u availability of systems

w application of single failure criterion

w loss of off-site power

u Nodalization and plant modelling

w user effects and user qualification

u application of Dsa to safety analysis of NPPs

u application of Dsa to a typical design basis accident

w loss of coolant accident (loca)

u introduction to computer codes for loca analysis

w code verification and validation

w experimental studies for code validation

w typical loca analysis

u introduction to analysis of beyond Design basis accidents (bDbas) and severe accidents (sas)

u regulatory review of Dsa

u relation of Dsa to

w engineering aspects of safety

w Probabilistic safety analysis

ATTENDEES WILL LEARN AbOUT

u safety analysis approach

u identification of Pies and their categorization

u conservative and bePu approaches for deterministic safety analysis of NPPs

u consideration of non-availability of systems and the effects of nodalization and plant modelling

u application of Dsa to a typical Dba such as loca

u basics of computer codes for loca analysis

u Verification and validation of computer codes

u introduction to analysis of bDbas

u regulatory review of Dsa

WhO ShOULD ATTEND?

u Nuclear safety advisors and consultancy firms

u engineering design consultants and technical service providers in the nuclear sector

u organizations (manufacturing, ePc, utility companies) serving and/or planning to enter the nuclear sector

u employees of NPPsu Personnel of NPP design, construction

and operating organizationsu representatives from energy

departments of the governmentu environmental protection agencies u Personnel involved in the safety

analysis of NPPsu regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme on safety analysis of NPPs. to get optimum benefits from the programme, participants should have knowledge of nuclear reactors and power plants. Knowledge of the basics of two-phase flow and nuclear safety aspects will be useful. the minimum qualification of the participants for attending the programme is a bachelor’s degree in science/ engineering. it is advisable to attend the programme on ’introduction to Nuclear safety’ before attending this programme.

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OM01reliability centred Maintenance

a nuclear power plant has a large number of equipment, systems and components including those critical for operation and safety. the complexity of an NPP and the associated economics of plant operation and power generation demand that good engineering and maintenance practices be utilized for reliability improvement and overall cost effectiveness. an operating plant generally has a planned programme based on preventive/corrective maintenance activities. this programme deals with a systematic approach to the design, development and evaluation of a cost-effective maintenance programme that is based on case studies and international experience to enhance the maintenance planning capabilities.

MODULESu introduction to rcM and background

u reliability centred maintenance

w existing maintenance practices versus rcM

w Principles of rcM

w the rcM process

u Practical applications

w system selection

w Qualitative analysis – failure modes, effects and criticality analysis

w field failure and maintenance data

w trend analysis

u benefits of rcM programme

w improvements in reliability

w cost benefits

w identification of ageing effects

u case studies and international experience in rcM

w case study involving Motor operated Valves (MoVs) in an NPP

w international experiences

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Operations and Maintenance

ATTENDEES WILL LEARN AbOUT

u the principles of rcM and the process

u New maintenance planning techniques

u selection of systems for the application of rcM

u failure modes, effects and criticality analysis

u Generation of failure and maintenance data from the field

u trend analysis and utilization of the data

u incorporating quality and reliability concepts in existing maintenance practices

u improvement in reliability and cost benefits

u identification of ageing trends

u case studies and international experiences

WhO ShOULD ATTEND?

u Process and plant engineers working in NPPs

u operations and maintenance staff of NPPs

u Personnel of industrial plantsu Personnel of power plants u Qa and reliability professionals in a

broad spectrum of industries u reliability consultantsu Government bodies dealing with the

energy sectoru regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. to derive maximum benefit from the programme, the participants should have a diploma/bachelor’s degree in science/engineering. this programme will be very useful to those involved in operation and maintenance activities.

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OM02efficient and safe operation of Nuclear Power Plants

the efficient and safe operation of a nuclear power plant calls for well trained and qualified operating personnel. the training and certification of nuclear power plant operators is a long drawn process. this programme introduces participants to the best international practices adopted in the nuclear power plant operating organizations around the world. it details the organization of plant operations; and the responsibilities, functions and the required competency of the shift operating staff. the functions of various systems, inclusive of the protection and safety systems, are explained. an introduction is given to the operating limits and conditions and limiting safety system settings. the role of safety culture and the importance of incident reporting system are explained. the need for proper understanding and interpretation of the indications in the control room and taking appropriate corrective actions is emphasized. the use of emergency operating procedures for accident management and regulatory requirements are also dealt with.

MODULESu introduction to NPPs and their operation

u standard organization for plant operations

u responsibilities, functions and competency of the shift operating staff

u operator training and certification

u Various activities during the operating shift

u operational manuals and operating procedures

u Working of different systems

u Protection and safety systems

u introduction to operating limits and conditions

u limiting safety system settings

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Operations and Maintenance

u review and upgradation of the various operating procedures

u interpretation of control room indications

w Detection of abnormal behaviour and taking corrective actions

u introduction to safety culture at NPPs

w emphasis on safety during all activities

u emergency operating procedures and accident management

u Normal operation and abnormal incidents reporting

u station policies

u regulatory requirements

ATTENDEES WILL LEARN AbOUT

u NPP operation and associated activities

u operation organization, roles and responsibilities of the operating staff

u functioning of various systems of the NPP, inclusive of protection and safety systems

u operator training and certification

u operating limits and conditions, limiting safety system settings

u Detection of abnormal behaviour from control room indications and taking corrective actions

u emergency operating procedures and accident management

u incident reporting, safety culture and regulatory requirements

WhO ShOULD ATTEND?

u consultants to the nuclear industryu organizations (manufacturing, ePc,

utility companies) planning to enter the nuclear sector

u engineering design consultants and technical service providers in the nuclear sector

u employees of nuclear power plantsu employees of companies owning

NPPsu Nuclear power plant designersu Government bodies involved in the

energy sector u regulatory bodiesu Nuclear safety consultants

REQUISITE QUALIFICATION

the minimum qualification required for the participants is a bachelor’s degree in science/ engineering. to derive optimum benefit from the programme, it will be useful if the participants have knowledge of the basics of nuclear power plant and the various systems that constitute the plant. it is suggested that the participants attend the programme on ‘NPP engineering, control and safety’ before attending this programme.

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QM01Quality assurance for Nuclear Power Plants

Nuclear power plants are designed to perform under stringent limits and conditions. high levels of quality are specified to ensure plant safety not only during normal operation, but also during abnormal and accident conditions. this programme on quality assurance for nuclear power plants deals with the various quality assurance measures specified for different plant activities during the life cycle of the plant such as design, procurement, manufacturing, transportation, storage, construction, fabrication, installation, operation, maintenance, inspection, repair and modification of the plant systems, structures and components (sscs). Quality assurance records and audits, in-service inspection and condition monitoring and relevant codes and standards will also be dealt with.

MODULESu Principles and concepts of Quality

assurance (Qa)

u Qa during different phases of the NPP

u Qa policies and programmes

u Qa organization

u Qa document control

u Design Qa

w Design interface control, verification, control of design changes

u Procurement control

w supplier evaluation, inspection of material and manufactured items, handling, storage and shipping of material and equipment

u Qa during construction, installation and erection of equipment

u inspection and testing

u Qa during commissioning, operation and maintenance

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Quality Management

u Non-conformance control and corrective actions

u Qa records and audits

u in-service inspection (isi), quality control and condition monitoring

u applicable regulatory codes and standards

ATTENDEES WILL LEARN AbOUT

u objectives of quality assurance programme for NPPs

u introduction to various quality assurance principles

u Different phases of NPP and Qa

u Qa organization and documentation

u Qa during design, procurement, construction, commissioning, operation and maintenance

u Non-conformance control, maintenance of Qa records and audits

u introduction to applicable codes and standards

WhO ShOULD ATTEND?

u organizations engaged in the design and manufacture of equipment for NPPs

u engineering design consultants and technical service providers in the nuclear sector

u organizations (ePc, utility companies) planning to enter into the nuclear sector

u Qa specialistsu specialists from inspection and

certification agenciesu environmental protection agenciesu Government agencies dealing with

energy sectoru regulatory bodies

REQUISITE QUALIFICATION

this is an introductory programme. to get optimum benefits from the programme, knowledge of plant engineering will be useful. the minimum qualification of the participants for attending the programme is a bachelor’s degree in engineering.

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RM01Probabilistic safety assessment

Probabilistic safety assessment/ Probabilistic risk assessment (Psa/Pra) is a systematic and comprehensive methodology to evaluate the risk associated with nuclear or other facilities, which have the potential for accident sequences whose consequences may spill into the public domain. Psa focuses on accident sequences that can damage the plant’s reactor core and also challenge the surrounding containment structures, since these pose the greatest potential risk to the public. it can be used to examine how NPP systems and operators work together to ensure plant safety. Psa level 1 study is extremely useful in design analysis and subsequent system design improvement, particularly if performed during the early design and development stages. this programme deals in detail with level 1 Psa. Details of level 2 and level 3 Psa analyses will also be discussed briefly.

MODULESu safety assessment of NPPs

u risk analysis, risk perception and acceptability

u Different levels of risk analysis

u level 1 Psa Methodology

w Plant familiarization

w identification and analysis of initiating events

w system analysis

w accident sequences/event tree analysis

w common cause failures

w analysis of dependent failures

w human reliability analysis

w Data requirements including failure rate data

w Quantification of results – core/plant damage frequency

w importance, sensitivity, uncertainty analysis

u containment/Psa level 2 analysis

u consequence/Psa level 3 analysis

u application of Psa to NPPs

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Risk Management

ATTENDEES WILL LEARN AbOUT

u risk awareness, perception and aversion

u Different levels of Psa

u Data requirements and collection at a plant

u component, equipment, system reliability analysis

u human reliability analysis

u Quantification of potential accident probabilities and risk

u importance analysis and understanding various contributors to plant risk

u Possibilities of improvement in safety by design

u a better understanding of the contributions of engineered safety systems to safety/risk

u application of Psa to the quantification of risk from an NPP

WhO ShOULD ATTEND?

u senior managers/engineers in organizations planning to enter the nuclear sector

u consultants involved in the design of system and equipment for NPPs

u Personnel involved in safety assessment of NPPs

u Personnel engaged in reliability and risk studies

u consultants engaged in Qa of nuclear equipment and systems

u Governmental staff in environmental and energy departments

u regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. the participants should have a bachelor’s degree in science/engineering and preferably, knowledge of the basics of nuclear reactors and reliability engineering. attending the programme ’Nuclear Power Plant engineering, control and safety‘, prior to this programme, would be advantageous.

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DM01emergency Preparedness and response

experience has shown that even though utmost care is taken for ensuring safety in the design and operation of a nuclear power plant, accidents cannot be completely ruled out. hence, the need for emergency preparedness arose. this programme deals with an introduction to the emergency preparedness measures which should be in place to enable limiting the consequences following an accident situation and a consequent nuclear emergency. the details of various types of emergencies, the required response procedures and the designated response agencies are explained. the radiation protection measures to be taken are dealt with. the role of governmental infrastructure as well as the responsibilities and the role of the regulatory body are also explained. the need for considering emergency response aspects at the site selection stage itself and the need for periodic emergency exercises to ensure the proper functioning of the response machinery during an emergency are also dealt with

MODULESu an introduction to NPPs

u Design of an NPP to meet the safety requirements and prevention of accidents

u safety systems and physical barriers for the prevention of radiation releases

u accident management and emergency preparedness

u emergency preparedness in safety infrastructure for a national nuclear power programme

u introduction to emergency preparedness and planning

u Plant emergency

u site emergency

u off-site emergency

u emergency preparedness and response organization

u emergency preparedness procedures

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Disaster Management

u Documentation and records of emergency preparedness

u responsibilities of various authorities during emergencies

u Governmental infrastructure for emergency preparedness and response

u radiation protection measures during emergencies

u capabilities for response to radiological emergencies

u emergency exercises and testing of emergency preparedness measures

u regulatory basis for emergency preparedness and responsibilities of the regulatory body

u considerations of emergency response in site survey and site selection for a nuclear installation

ATTENDEES WILL LEARN AbOUT

u importance of nuclear safety and radiation protection

u safety systems and physical barriers for the prevention of radiation releases

u accident mitigation, management and handling of emergencies

u Different types of emergencies

u emergency preparedness and planning

u Governmental organization and infrastructure for handling emergencies

u responsibility of various emergency response authorities

u intervention levels and radiation protection measures

u emergency exercises to test the effectiveness and availability of emergency response infrastructure and various provisions

u role of the regulatory body

WhO ShOULD ATTEND?

u Government bodies dealing with emergencies

u disaster management organizationsu Non-governmental organizations

identified to play a role during nuclear emergencies

u consultants attached with emergency response agencies and organizations

u emergency response equipment designers, manufacturers and suppliers

u Governmental staff in environmental and energy departments

u organizations involved in energy and environmental work

u Doctors trained to treat radiation effects and injuries

u Nuclear power plant personnelu regulatory bodies

REQUISITE QUALIFICATION

this is an advanced programme. to benefit from this programme, the participants should have a bachelor’s degree in science/engineering. it will be useful to have knowledge of the basics of NPPs, radiation effects and handling of emergencies.

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DE01Decommissioning of Nuclear Power Plants

the decommissioning of a nuclear power plant at the end of its life is a very complex task. appropriate provisions and early actions to facilitate the decommissioning process will help in accomplishing this task, without major problems, at the end of the plant life. the purpose of this programme is to provide information on the basic steps in the decommissioning process, various factors to be taken into account and the issues to be considered. the elements included in the programme will assist in decision-making, planning, and implementation of the task. an assessment of alternative strategies will be useful. the programme covers various aspects such as project planning, organization for management and execution, dismantling, decontamination, waste management and so on. the environmental and safety concerns as well as the regulatory aspects related to decommissioning will also be covered in the programme.

MODULESu introduction to decommissioning

u safety objectives of decommissioning

u Provisions/considerations facilitating decommissioning

u factors influencing decommissioning

u strategies and planning for a decommissioning project

u organization for decommissioning

w Delineation of responsibilities and functions

u Quality assurance

u Protection criteria

w health and safety considerations

u Decommissioning process/activities

u Decontamination

u Waste management

u regulatory aspects of decommissioning

u environmental and safety aspects

u Documentation and records

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Decommissioning

ATTENDEES WILL LEARN AbOUT

u the need for decommissioning

u basic steps involved in the decommissioning of a nuclear power plant

u Planning, management and execution of a decommissioning project

u responsibilities and functions of the parties involved in the decommissioning project

u Protection criteria

u health and safety considerations

u Decommissioning, decontamination and waste management

u environmental and safety aspects

u regulatory issues

WhO ShOULD ATTEND?

u Nuclear facility operatorsu engineering and consulting firms

dealing with the nuclear sectoru Personnel engaged in radiation

protection activitiesu NPP personnelu employees of NPP owning and

operating organizationsu Decommissioning and radiation

protection equipment designers and manufacturers

u Decommissioning and radiation protection equipment suppliers

u Government staff of departments designated for the implementation of radiation safety

u environment ministry staffu staff interested in advancing their

knowledge of radiation protection and safety in tasks that involve handling large quantities of radioactive wastes

u regulatory bodies

REQUISITE QUALIFICATION

this is an introductory programme on the decommissioning of a nuclear facility. to get optimum benefits from the programme, it will be useful if the participants have basic knowledge of nuclear reactors and power plants and radiation protection. the minimum required qualification of the participants attending the programme is a bachelor’s degree in science/engineering.

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coNtact iNforMatioN

WORLD NUCLEAR UNIVERSITyCOORDINATING CENTRE (WNUCC)22a st James’s squarelondon sW1y 4Jh, uK+44 (0)20 7451 1520www.world-nuclear-university.org

Steve [email protected]

François [email protected]

PM DIMENSIONSSUPPORT TEAM

PM Dimensions is a multinational company headquartered in Mumbai and focussed on delivering workforce training and engineering services to major companies and institutions. PMD has brought its extensive experience to bear in shaping and supporting delivery of the WNu Workforce Development curriculum.

Alfred GeorgeM: +91 94 22 369 223o: +91 22 67349827

Dr. kaluba ChitumboM: +43 6769319989

for further queries email at: [email protected]