Educational and technological internship for students is a type of training directly focused on professional and practical training of students under the program “Emergency Preparedness and Response (International Educational Program)” of Peter the Great St. Petersburg Polytechnic University. Qualified personnel of Rosatom’s ERC, JSC, which was created specifically to organize and conduct emergency rescue and other urgent works in radiation accidents and incidents, conduct practical training in this area of training. The purpose of this practice is to form and consolidate professional knowledge, skills and abilities acquired as a result of the university theoretical training and previously acquired practical skills. As stated in the publication of the International Atomic Energy Agency (IAEA) “Preparedness and Response to a Nuclear or Radiological Emergency”: “The practical objective of emergency response is to provide a timely, manageable, controlled, coordinated and effective response at the scene, as well as at the local, regional, national and international levels, to any nuclear or radiological emergency”. International basic safety standards for working with radiation sources and methods of protection against ionizing radiation were developed on the basis of scientific research. In 1957, there was the IAEA under the United Nations (UN). The systems of state guarantees of safety in the use of atomic energy of the Russian Federation are established in an extensive legislative framework. The main document of this legal framework in the Russian Federation is the Constitution of the Russian Federation. Universally recognized principles and norms of international law and international treaties of the Russian Federation are an integral part of its legal system and have priority over the law. In the Russian Federation there are federal laws: “On Radiation Safety of the Population” No.3-FZ dated January 9, 1996; “On the Sanitary and Epidemiological Welfare of the Population” No.52-FZ dated March 30, 1999, etc. Radiation safety standards (NRB-99/2009) define the decision-making procedure for activities ensuring occupational safety of personnel and population. The present manual is based on the above-mentioned regulatory documents. The solution of tasks in the field of emergency preparedness and response largely depends on a timely and competent assessment of the radiation situation in the area affected by radiation contamination, both in the initial and in the later stages of the accident. The main measures to protect the population are based on a competent calculation, subsequent selection and implementation of radiation protection modes of the population. This manual is a guide on how to solve possible problems in the field of emergency response and is an instruction on how to maintain a high culture of nuclear and radiation safety. This manual presents the procedure of training-technological practice, which defines the concept of ensuring radiation safety, requirements to the infrastructure and functional requirements in the field of emergency preparedness and response, the main ways of solving the tasks of assessing the radiation situation.

• CONTENTS
• LIST OF ABBREVIATIONS
• Introduction
• 1. Organization of emergency response
  • 1.1. Purpose of the work
  • 1.2. Tasks
  • 1.3. The procedure of organizing emergency response
    • 1.3.1. Initial response
    • 1.3.2. Response at the accident site
    • 1.3.3. Radiation response
  • 1.4. Description of the required equipment
  • 1.5. Task performance algorithm
• 2. Field monitoring of radiation and contamination level
  • 2.1. Purpose of the work
  • 2.2. Tasks
  • 2.3. Specific features of field monitoring of radiation and contamination levels
    • 2.3.1. Quality control of operation of radiation devices
    • 2.3.2. Exploration in the cloud
    • 2.3.3. Exploration of landfall
    • 2.3.4. Environmental dosimetry
    • 2.3.5. Source monitoring
    • 2.3.6. Exploration of surface contamination
  • 2.4. Description of the required equipment
  • 2.5. Task performance algorithm
• 3.Sampling
  • 3.1. Purpose of the work
  • 3.2. Tasks
  • 3.3. Environmental sampling
    • 3.3.1. Air sampling
    • 3.3.2. Soil sampling
    • 3.3.3. Water sampling
  • 3.4. Description of the required equipment
  • 3.5. Task performance algorithm
• 4.Methods and means of personnel protection
  • 4.1. Purpose of the work
  • 4.2. Tasks
  • 4.3. Theoretical review of methods and means of personnel protection
    • 4.3.1. Protection against exposure to ionizing radiation
    • 4.3.2. Personal protective equipment
  • 4.4. Description of the required equipment
  • 4.5. Task performance algorithm
• 5. Dose estimation
  • 5.1. Purpose of the work
  • 5.2. Tasks
  • 5.3. Assessment of radiation doses. Main routes of dose accumulation
    • 5.3.1. Dose assessment overview
    • 5.3.2. Point source, line source
    • 5.3.3. Ground contamination, skin contamination, inhalation intake of radionuclides
    • 5.3.4. Assessment radionuclides concentration in air
    • 5.3.5. Activity calculation
  • 5.4. Description of required equipment
  • 5.5. Task performance algorithm
• 6. Identification of radioactive sources
  • 6.1. Purpose of the work
  • 6.2. Tasks
  • 6.3. γ-spectrometry
  • 6.4. Description of the required equipment
  • 6.5. Task performance algorithm
• 7. Methods and means of radiometric measurements
  • 7.1. Purpose of the work
  • 7.2. Tasks
  • 7.3. Description of measurement of total alpha, beta activity in water samples
  • 7.4. Description of the required equipment
  • 7.5. Task performance algorithm
• 8. Radiochemical analysis
  • 8.1. Purpose of the work
  • 8.2. Tasks
  • 8.3. The essence of the method of tritium analysis by simple distillation
  • 8.4. Description of the required equipment
  • 8.5. Task performance algorithm
    • 8.5.1. Sample preparation by simple distillation
    • 8.5.2. Preparing the radiometer and equipment for operation
• 9. Individual contamination monitoring and decontamination
  • 9.1. Purpose of the work
  • 9.2. Tasks
  • 9.3. Theoretical fundamentals of contamination monitoring and decontamination
    • 9.3.1. Basics of monitoring and organization of decontamination
    • 9.3.2. Contamination monitoring
  • 9.4. Description of the necessary equipment
  • 9.5. Task performance algorithm
• 10. Mobile radiation monitoring systems
  • 10.1. Purpose of the work
  • 10.2. Tasks
  • 10.3. General provisions
  • 10.4. Description of the required equipment
  • 10.5. Task performance algorithm
• 11. Assessment and prognosis during a nuclear or radiological emergency
  • 11.1. Purpose of the work
  • 11.2. Tasks
  • 11.3. Modern methods and tools of forecasting the consequences of radiation accidents
    • 11.3.1. Fundamentals of atmospheric dispersion
    • 11.3.2. Modern Decision Support System
    • 11.3.3. Subsystem of Managing of DSS
    • 11.3.4. Basic services IBD
    • 11.3.5. Operative Data Base
    • 11.3.6. Calculation Modules
    • 11.3.7. Client Part
    • 11.3.8. Modeling the consequences of radiation accidents
  • 11.4. Description of the required equipment
  • 11.5. Task performance algorithm
• 12. Assessment and prognosis during a nuclear or radiological emergency
  • 12.1. Purpose of the work
  • 12.2. Tasks
  • 12.3. Assessment of the parameters for decisions making in case of a radiation accident
  • 12.4. Description of the required equipment
  • 12.5. Task performance algorithm
• 13. Assessment and prognosis during a nuclear or radiological emergency
  • 13.1. Purpose of the work
  • 13.2. Tasks
  • 13.3. Ways to improve the accuracy of forecasting the estimated parameters
  • 13.4. Description of the required equipment
  • 13.5. Task performance algorithm
• 14. Simulation of multi-unit accidents at nuclear power plants
  • 14.1. Purpose of the work
  • 14.2. Tasks
  • 14.3. Modern approaches and methods for modeling a multi-unit accident
    • 14.3.1. Operational intervention levels (OILs)
    • 14.3.2. OIL1, OIL2 and OIL3 for ground deposition dose rates
    • 14.3.3. Plain language explanations for OILS
  • 14.4. Description of the necessary equipment
  • 14.5. Task performance algorithm
    • 14.5.1. Radiation scenario of a simulated accident
• 15. Use of other software tools for estimating radiation parameters
  • 15.1. Purpose of the work
  • 15.2. Tasks
  • 15.3. Modern approaches and methods for modeling a multi-unit accident
    • 15.3.1. Modeling the radiation field of a radiation source
    • 15.3.2. Modeling of PM dispersion during explosive explosion
  • 15.4. Description of the necessary equipment
  • 15.5. Task performance algorithm
    • 15.5.1. The task of modeling the radiation field of a radiation source
    • 15.5.2. The task of modeling the dispersion of PM during an explosive explosion
• Conclusion
• References
• Appendix А
• Appendix B
• Appendix C
• Appendix D
• Appendix E
• Appendix F
• Appendix G
• Appendix H
• Appendix I
• Appendix J
• Appendix K