This Regional training module is dedicated to safety and regulatory aspects of nuclear facilities particularly focused to research reactors. It includes the safety requirements, safety analysis methodology, the defense-in-depth and application of graded approach. The course includes hands-on-training on research reactor located near Rabat. This Regional training module is dedicated to safety and regulatory aspects of nuclear facilities particularly focused to research reactors. It includes the safety requirements, safety analysis methodology, the defense-in-depth and application of graded approach. The course includes hands-on-training on research reactor located near Rabat.
Available courses
The Training Module on I&C and Electrical Systems provides the trainees with fundamentals and applications in the field of reactor instrumentation and plant control and electrical systems, as well as the state-of-the-art of the International Requirements on this field. The training is intended to refer both to Nuclear Power Plants and Research Reactors issues. This training course is intended for engineers who wish to acquire general knowledge of the I&C and Electrical Systems operation, technology and safety for nuclear facilities (nuclear power plants, research reactors and fuel cycle facilities) in normal and accident conditions. It primarily addresses the needs of professionals from regulatory bodies and technical support organizations as well as operators and licensees.
The objective of this training is to improve knowledge in the activities of nuclear regulatory authorities and technical support organizations with respect to the regulatory control of radiation protection in medical applications (radiotherapy, nuclear medicine and diagnostic and interventional radiology).
This training concerns professionals from nuclear regulatory authorities or technical support organizations involved in the licensing and inspection of medical activities or facilities utilizing sources of ionizing radiation.
This training is organized in the framework of the Instrument for Nuclear Safety Cooperation of the European Commission. The objective is to provide a detailed overview (concepts and methods) in the field of Human and Organizational Factors (HOF). This training is intended for:
- engineers,
- researchers,
- other professionals from Nuclear Regulatory Authorities and Technical Support Organisations involved in nuclear safety activities.
The five-day training module will cover the following subjects:
- The Überlingen Accident working group.
- Introduction to Human and Organizational Factors: key concepts and methods.
- From human error to organizational reliability.
- Human and organizational factors in design.
- Human and organizational factors in operation.
- Human and organizational factors in dismantling.
- Operating experience feedback and event investigation.
- Analysis of an event.
- Working groups.
- Man-machine interface and control-room supervision.
- Human and organizational factors and nuclear assessment.
- Human reliability analysis.
- Crisis management.
- Safety culture.
This training course is organised in the framework of the Instrument for Nuclear Safety Cooperation of the European Commission. Regulatory oversight of operating Nuclear Power Plants (NPP) is a key aspect in assuring safe NPP operation and proper adherence to licensing basis as required in plant authorization This training course is intended for technical personnel of regulatory bodies and Technical Support Organizations (TSO) who pursue to acquire general knowledge in the assessment of important safety related aspects regarding NPP operation and the most significant features of a risk informed, comprehensive regulatory oversight system of such aspects. Attendees are expected to have sufficient engineering background on NPP and previous general knowledge on regulatory activities.
This training is organized in the framework of the Instrument for Nuclear Safety Cooperation of the European Commission. The objective is to provide a detailed overview (concepts and methods) in the field of Human and Organizational Factors (HOF). This training is intended for:
- engineers,
- researchers,
- other professionals from Nuclear Regulatory Authorities and Technical Support Organisations involved in nuclear safety activities.
The five-day training module will cover the following subjects:
- The Überlingen Accident working group.
- Introduction to Human and Organizational Factors: key concepts and methods.
- From human error to organizational reliability.
- Human and organizational factors in design.
- Human and organizational factors in operation.
- Human and organizational factors in dismantling.
- Operating experience feedback and event investigation.
- Analysis of an event.
- Working groups.
- Man-machine interface and control-room supervision.
- Human and organizational factors and nuclear assessment.
- Human reliability analysis.
- Crisis management.
- Safety culture.
The training will start by recalling the basics on quality control, quality assurance and their evolution to Quality Management System and Integrated Management System. The requirements of international standards (ISO, IAEA…) will be discussed and compared in order to understand their respective approach, similarities and differences. Emphasis will be given on the process approach as recommended by IAEA in its recent publications and also on important issues like satisfaction of interested parties, graded approach, continuous improvement, transparency, communication to the public. A part of this training will be also devoted to introduce the importance concept of Safety Culture and provide examples of its integration in the Management System. Examples will be presented to show how the requirements from ISO 9001 and IAEA GS-R-3 are implemented in some Management Systems.
A five day training module addressing regulatory control of the radiation safety hazards associated with mining and processing of minerals containing elevated levels of naturally occurring radionuclides. It discusses the radiation hazards associated with mining and processing of uranium and other minerals containing elevated levels of naturally occurring radionuclides. The course presents the safety principles applied to natural radioactivity and discusses the associated regulatory processes including the establishment of safety standards, regulatory review of safety assessments, establishment of conditions of authorisation and the implementation of regulatory compliance assurance programmes including inspection. Operational radiation protection of workers in surface installations and underground will be covered and protection of the public and environmental surveillance will be covered. The course will address management of radioactive waste arising from mining and minerals processing operations and will deal with the legacy issue associated with existing or abandoned facilities.
The course is based on generic case study to address crisis decision management. The scenario considers an attack on an NPP requesting an emergency response at national level and provides successive failures of safety functions requiring timely and appropriate measures to be taken to stop the aggression and restore safety and security on the site. The course is a scenario driven with time-stepped facilitated discussion. The module consists of three days of training. The scenario is divided into four phases and nine sequences, each addressing a homogeneous stage of the emergency situation: ▪ Reflex phase: - First sequence: the attack, ▪ Reflection phase: - Second sequence: first statement/first response, - Third sequence: emergency management deployment, - Fourth sequence: failure of first actions, - Five sequence: analysis of the situation, - Sixth sequence: intervention strategy, - Seventh sequence: decision-making process for assault, ▪ Response phase: - Eighth sequence: assault by SWAT, ▪ Recovery phase: - Ninth sequence: recovery strategy.
This training presents the main issues related to reliability for design, failure, modes and effects analysis, reliability data estimation, Probabilistic Safety Assessment (PSA), analysis of event sequences including severe accidents, component qualification and reliability, uncertainty and sensitivity analysis, risk-informed decision making.
The training course is intended for professionals employed by nuclear regulatory authorities and technical support organizations involved in nuclear safety activities.
When operations are performed on fissile materials outside nuclear reactor cores (storage facilities, laboratories, factories and transport), these operations present a particular risk: the risk of criticality. The nuclear criticality safety is the prevention of nuclear criticality accidents and the limitation of the consequences of such accidents they should occur.
This training provides basic knowledge on nuclear criticality safety, and concerns person responsible for design, fabrication or maintenance of nuclear criticality safety for a process or facility. These persons would be nuclear criticality safety specialists with the responsibilities of assessment, calculation or peer review of nuclear criticality safety documentation. Also, Individuals or bodies with responsibilities of oversight and regulation of facilities and processes.
Concerned area:
▪ fissile material transportation.
▪ fuel cycle plants (fuel manufacturing, recycling, etc).
▪ laboratories and fissile materials storage.
▪ reactor core in loading and unloading.
▪ plants permanently shut down or being dismantled
This Enstti Training course starts by the overview of decommissioning aspects and the presentation of ongoing decommissioning projects (NPPs and fuel cycle facilities). This will ensure that all participants share the same understanding of decommissioning and will set the scene for the further lectures. Second day will start with the presentation of the methodologies for safety assessment and regulatory review of safety assessment implemented in France. This will be the starting point for lectures point for lectures performed by specialists addressing the risks identification, human factors, radiation protection, fire safety, risks linked to handling activities during decommissioning and radiological characterisation vs waste management. To illustrate how to deal with these issues, a test case in radiation protection during decommissioning will be proposed to the participants. In addition, during this training, a specific session will be dedicated to innovative techniques for decommissioning related to 3D simulation and contaminated site characterization with geostatistics concepts.
The objective of this training module is to provide the trainees with a practical knowledge of the issues, objectives, methods and tools required for the analysis of experience feedback from nuclear facilities.
The training course is intended for professionals involved in activities related to nuclear-facility safety monitoring and assessment.
The main objective of the training is to use the CRISTAL V2 package for criticality calculations with LATEC graphical frontend and simulation back-end with CRISTAL codes (APOLLO2, MORET 5 et TRIPOLI-4®).
Underlying numerical recipes of simulation and their limitations in the criticality-safety assessment framework are described. This training is designed to meet the needs of nuclear criticality safety practitioners.
This training concerns person and organization responsible for design, fabrication, maintenance or review of nuclear criticality safety for a process or transportation. These persons would be Nuclear criticality safety specialists with the responsibilities of assessment and calculation.
CRISTAL package is used to performed calculations for:
▪ fissile materials transportations.
▪ nuclear fuel cycle facilities (fuel
processing, reprocessing…).
▪ laboratories and storage units.
▪ unloaded nuclear reactor core.
▪ decommissioning or decommissioned facilities.