Training REACTOR SAFETY NUCLEAR SAFETY - 1 SAFETY IN PWR, BWR, CANDU, VVER, RBMK FOR REGULATORS, OPERATORS AND LICENSORS. May 2-6, 2016 – ENEA Research Center, Bologna, Italy Distinguished members of scientific community, whenever possible, do not miss the opportunity to underline the importance to improve the knowledge on safety issues and safety culture in the nuclear reactor field. Exchange of information among scientists and promotion of courses and modules for education and training, specially those addressed to young generations and to newcomers (no matter if single persons or countries) are strongly encouraged. It is the third year that has ENEA organized a “Nuclear Reactor Safety -I” module to capture the attention and the interest of international attendees, focusing on the absolute importance of safety issues in the nuclear field. Previous editions indicate that participants gained significant advantages having attended this module.

WHO SHOULD ATTEND This training course is intended, in the main, for graduates of engineering, chemistry, and physics who wish to acquire a general knowledge of the strengths and weaknesses of PWR, BWR, CANDU, VVER, RBMK, both during normal operation and under severe accident scenarios. All reactor peculiarities are described, starting from neutronics and thermal hydraulics of the most important reactor systems and arriving to the containment/confinement description and safety analysis of active and passive systems. The scope of this module makes it highly suitable for professionals working in the regulatory field, as well as for operators and licensees. Head Office 12, rue de la Redoute 92260 Fontenay-aux-Roses France Phone: +33 (0)1 58 35 72 32 E-mail: [email protected] Mailing Address BP 89 92261 Fontenay-aux-Roses Cedex France

LEARNING OUTCOMES  Description and critical investigation of western and eastern reactors like PWR, BWR, CANDU, VVER and RBMK (the last mainly for accident reasons).  Fuel and core design optimization in western and eastern reactors.  Neutronics, thermal hydraulics and containment characteristics of western and eastern reactors.  Introduction and description of main aspects referring to deterministic and probabilistic safety analysis, event trees, fault trees, core damage frequency.  Physical barriers and design approach (negative reactivity, fuel pellet, cladding, reactor vessel, containment building).  Description of relevant accident scenarios with a thorough look at safety aspects.  Malfunctions Reduction rate (redundancy, separation, differentiation).  External Events Minimizing (anti-seismic construction, breakwaters, fences).  Air- and ground-concentration, in the near field, of radionuclides released to the environment as gases, aerosols or particulates.  Safety Authority Regulations and procedures (human error, quality control, inspections).  Detailed information of the decommissioning operations needed to dismantle a nuclear power plant.  Development and verification of accident management procedures.

PROGRAM The training course is divided into well balanced lectures, practices (working groups), round table discussions and terminates with a final examination to verify the level of learning acquired by attendees. The aim of lectures is to present and explain advanced concepts in all topics indicated in the “learning outcomes” section. Working group practices are a challenge to probe one’s ability with simulation tools. Each participant is called to become active part in the simulation of some of the most relevant cases and reactor accident situations. It is a very useful skill for licensing and supervision process. Discussion time will be organized with and by the lecturers. This module is finalized to give to attendees an overview of the main characteristics of LWRs, both under normal operation conditions and during transients and accidents. Some of the most relevant transients are investigated to verify whether a severe accident may occur or not. It is evident that common information do not correspond perfectly to PWRs and BWRs, even if all LWRs are characterized by similar parts and components. This is the reason why the first part of all lectures will make focus on the following general items: - Main aspects of Neutronics - Main aspects of Thermal Hydraulics - Fuel and Core Design - The Defence in Depth Concept - Safety assessment methods - Design Basis Accident - Severe Accidents.

The second part will make major focus on the very specific items and topics that characterize the main differences among the various reactors typologies. Each lecture will be described by specific key words, educational objectives, general and specific aspects of reactor types, peculiarities and ways of reactions under different operational and accidental stresses.

EXAMINATION A final multiple-choice examinationwill be held on the last day.

TEACHING METHODS The instructional method is based on a combination of lectures and practical exercises using examples and experience feedback. Accident events really occurred will be described, explained, analysed and discussed with participants. The working groups will be organized to simulate, by means of computer tools, some relevant accident sequences.

PRICE AND REGISTRATION  The price for this course is €2,500. Fees cover instruction, documentation, technical visits and lunch and coffee breaks during days’ course.  To register complete and submit the online ENSTTI form. Select: Nuclear Reactor Safety - I.  Registration Deadline for participants from partners countries: March 10, 2016  Registration Deadline for other participants: April 10, 2016

Training NUCLEAR REACTOR SAFETY – I May 2 – 6, 2016 – Bologna, Italy

Type

Description

Lenght

Day 1: Safety Requirements, PWRs (full treatment), BWRs (Neutronics)  A01 - The evolution of safety requirements in NPPs Class room

 A02 - PWRs - Neutronics  A03 - PWRs – System & Containment

1 day

 A04 - BWRs - Neutronics Day 2: BWRs (System & Containment), VVER (full treatment), LCA and Codes  B01 - BWRs – System & Containment Class room

 B02 - VVER – Safety concepts & Technologies  B03 - NPPs operation & life cycle assessment

1 day

 B04 - Nuclear application of simulation tools Day 3: Working Groups and simulation exercises in computer room Working Groups (computer room)

 C01 - Simulation tools – PART “A1  C02 - Simulation tools – PART “B1”2  C03 - Simulation tools – PART “B2”2

1 day

 C04 - Simulation tools – PART “C”3

Day 4: CANDU and RBMK (full treatment)  D01 - CANDU – Neutronics  D02 - CANDU – System & Containment Class room

 D03 - RBMK – Neutronics

1 day

 D04 - RBMK – System & Containment Day 5: Regulatory Requirements, Decommissioning (Ignalina), Examination  E01 - Regulatory requirements and their implementation Class room

 E02 - Decommissioning activities - Ignalina

1 day

 E03 – Test  E04 - Summary and closure Assessment

1

Test to assess knowledge acquired during the training

Teacher-learner interaction (teachers explain the exercises to be performed by learners). Exercises (learners alone, to perform exercises). 3 Learner-teacher interaction (learners present the performed exercises to teachers). 2