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Post diploma in power plant engineering, safety & technology [IAEA Standard]

The course presents the principles and key issues of nuclear safety, including the following topics:

In this course, students explore the engineering design of nuclear power plants using the basic principles of reactor physics, thermodynamics, fluid flow and heat transfer. Topics include reactor designs, thermal analysis of nuclear fuel, reactor coolant flow and heat transfer, power conversion cycles, nuclear safety, and reactor dynamic behavior.

The purpose of this qualification is to disseminate lessons learned information regarding training and human resource considerations for commissioning of nuclear power plants (NPPs).The IAEA technical working group on training and qualification of nuclear power plant personnel. Subject cover the experiences gained regarding commissioning training for nuclear power plant projects This recommendation was made in recognition that in many of the Member States with operating nuclear power plants it has been some years since an NPP has been commissioned, and most of the staff with experience in commissioning have since retired. Additionally, in a number of Member States serious consideration is being given to initiating new nuclear power programmes. This publication is intended to provide useful information for both of these situations.

This Qualification is intended to apply to commissioning of NPP projects in Member States that are initiating their nuclear power programmes, as well as in those Member States with established nuclear power programmes.

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It provides recommendations on fulfilling the Safety requirements on Safety of Nuclear Power Plants:

Students will be able to recognize and recall the basics of nuclear reactor terminology, definitions, and concepts associated with reactor physics and theory and technology of nuclear power plant. Students will learn principals of water chemistry control for nuclear power plant systems.

Students will classify different materials and alloys in power plant application and describe effects of radiation on them such as fracture of nuclear fuel, stress development in the reactor vessel wall, erosion/corrosion effects.Students will apply their knowledge of basic electrical theory, basic alternating current (AC) and direct current (DC) theory in application to nuclear power.

Students will apply their knowledge of mechanical engineering principals to the theory of valve fundamentals and components, pumps, turbines, vibration, rotating equipment safety.Civil engineering design principals and considerations will be named.The construction and principle of operation of the different sensing and indicating devices used at power plants will be explained to students.

  • Radiation protection in nuclear facilities;
  • Design of a nuclear reactor, interfaces with security;
  • Safety classification of structures, systems and components;
  • Deterministic accident analysis and probabilistic safety analysis;
  • Links between probabilistic, deterministic analysis and risk informed decision making;
  • Sitting considerations and environmental impact assessment;
  • Operational safety, including operational feedback;
  • Limiting conditions for operation;
  • Plant renewals, modifications and upgrades, ageing;
  • Maintenance and surveillance programmes;
  • In-plant accident management and emergency preparedness and response;
  • Safety of the fuel cycle, management of spent fuel and safety of transport of radioactive material;
  • Decommissioning and waste management;
  • Regulatory control;
  • Management system, leadership and safety culture;
  • Human performance;
  • Public communication

Contents

1. OVERALL TRAINING AND HUMAN RESOURCE ISSUES FOR COMMISSIONING
1.1. Terminology and background
1.2. Types of NPP projects and their structures
1.3. Considerations regarding training and HRM issues for turnkey and split- package contracts
1.4. Staffing plans for the commissioning phase
1.5. Training programmes and plans
1.6. Training materials for commissioning
1.7. Control room simulator training
1.8. Training organization for commissioning
1.9. Use of system engineers

2. Training of maintenance staff, and other plant personnel during commission

3. TRAINING AND HUMAN RESOURCE ISSUES FOR SPECIFIC SITUATIONS
3.1. Issues for the first NPP in a country or organization
3.2. Specials issues for the FOAK Plant added to an existing fleet
3.3. Special issues for rapid expansion of an existing NPP fleet

3. MANAGEMENT AND ORGANIZATION OF PLANT OPERATIONS

  • Functions and tasks of plant operations
  • Operating policy
  • Human resources and qualification of personnel
  • Performance objectives and standards
  • Interfaces with other plant groups

4.SHIFT COMPLEMENT AND FUNCTION

  • Shift supervisor
  • Operators
  • Shift safety engineer or technical adviser
  • Shift technical support personnel

5. SHIFT ROUTINES AND OPERATING PRACTICES

  • Shift arrangements
  • Shift operations
  • Shift turnover
  • Availability and use of operating procedures
  • Pre-job briefings
  • Conduct in the control room
  • Shift rounds
  • Communications
  • Shift records and log keeping

6. CONTROL OF EQUIPMENT AND PLANT STATUS

Labeling of plant equipment

7. HUMAN RESOURCE CONSIDERATIONS FOR COMMISSIONING OF NPPS

TRAINING OF PERSONNEL FOR THE COMMISSIONING OF CERNAVODA NPP (ROMANIA)

8. OLKILUOTO 3 NUCLEAR POWER PLANT TRAINING AND HR ISSUES FROM THE NPP

OPERATING ORGANIZATION PERSPECTIVE (FINLAND)

9. TRAINING OF MANPOWER FOR COMMISSIONING PROJECTS TAPP- CASE STUDY (INDIA)

10. SHIN WOLSONG CONSTRUCTION AND COMMISSIONING,TRAINING IN KHNP (ROK

11. KHNP STAFFING PLAN OF CONSTRUCTION SITE OFFICE: LCHIN 5&6 CONSTRUCTION PROJECT (ROK)

  • Full Digital I&C and HMIT Systems
  • Study on Modeling of an Integrated Control and Condition
  • Monitoring System for Nuclear Power Plants
  • A Toolkit for Computerized Operating Procedure of Complex Industrial Systems with IVI-COM Technology
  • Development and Design Guideline for Computerized Human–Machine Interface in the Main Control Rooms of Nuclear Power Plants
  • Risk Monitor Methods for Large and Complex Plants
  • Overview of System Reliability Analyses for PSA
  • A Systematic Fault Tree Analysis Based on Multi-level Flow Modeling
  • Reliability Graph with General Gates: A Novel Method for Reliability Analysis
  • Design of Risk Monitor for Nuclear Reactor Plants
  • Review of Practicing Level-2 Probabilistic Safety Analysis for Chinese Nuclear Power Plants
  • Risk Monitoring for Nuclear Power Plant Applications
  • Using Probabilistic Risk Assessment
  • Part III Condition Monitors for Plant Components
  • Condition Monitoring for Maintenance Support
  • Condition Monitoring to Enable Extended Operation
  • of Nuclear Power Plants
  • Using Condition-Based Maintenance and Reliability-Centered Maintenance to Improve Maintenance in Nuclear Power Plants
  • Advanced Management of Pipe Wall Thinning Based on Prediction-Monitor Fusion
  • Non-destructive Evaluation of Material State by Acoustic,
  • Electromagnetic and Thermal Techniques 21 Non-contact Acoustic Emission Measurement for Condition Monitoring of Bearings in Rotating Machines Using Laser Interferometry
  • Acoustic Monitoring of Rotating Machine by Advanced Signal
  • Processing Technology
  • The Wireless Diagnostic System for Motor Operated Valves
  • Part IV Virtual and Augmented Reality for Nuclear Power Plants
  • Virtual and Augmented Reality in the Nuclear Plant Lifecycle Perspective
  • A Feasibility Study on Worksite Visualization System
  • Using Augmented Reality for Fugen NPP
  • Augmented Reality for Improved Communication of Construction and Maintenance Plans in Nuclear Power Plants
  • 3D Representation of Radioisotopic Dose Rates Within Nuclear Plants for Improved Radioprotection and Plant Safety
  • Wide Area Tracking Method for Augmented Reality Supporting
  • Nuclear Power Plant Maintenance Work
  • Part V Software Reliability V&V for Nuclear Power Plants
  • Research on Software Systems Dependability
  • at the OECD Halden Reactor Project
  • High Level Issues in Reliability Quantification of Safety-Critical Software
  • 32 Software Reliability Analysis in Probabilistic Risk Analysis
  • Power Reactors
  • Reactor Systems
  • Uranium Enrichment.
  • Converter Reactors With a Thermal Neutron Spectrum
  • Breeder Reactors With a Fast Neutron Spectrum
  • Neutron Lifetime
  • Masses of Fuel, Fission Products and Actinides
  • Technical Aspects of Nuclear Fuel Cycles
  • Waste Disposal
  • Nuclear Fuel Cycle Options
  • Minor Actinides: Partitioning, Transmutation and Incineration10 Radioactive Releases from Nuclear Power Plants
  • Radionuclides
  • Nuclear Accidents
  • Summary of Safety Research Findings

THEORY PAPER:-

International Atomic Energy Agency (IAEA) Framework/ Organizational Structure (100 Marks)
Commissioning of Nuclear Power Plants – Training & Human Resource Considerations (100 Marks)

Probabilistic Risk Assessment for Nuclear Power Plants (100 Marks)
Progress of Nuclear Safety for Symbiosis and Sustainability (100 Marks)
Sustainable and Safe Nuclear Fission Energy (100 Marks)

PRACTICAL

Case studies on Nuclear Power Station Catastrophic Disaster investigations and subsequent recommendations. (400 Marks)


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