Workshop on the Development of Operating Programmes for Research Reactors
29 April - 3 May 2013
1. INTRODUCTIONInformation gathered from safety review missions to research reactors, as well as from discussions at Technical Meetings, has indicated that many Member States of the International Atomic Energy Agency (IAEA) that currently operate research reactors need to improve their operating programmes - including such aspects as the structure and management of the operating organization, the conduct of reactor operations, utilization and maintenance. Of particular concern is the question of how to manage the documentation related to the reactor and its associated experimental facilities, including the safety analysis report, operational limits and conditions, operating procedures, drawings of the facilities and their operational records. In some cases, the safety documents, procedures and drawings of structures, systems and components do not reflect the actual operating practices and physical status of the research reactor. This situation gives rise to safety concerns during day to day operation of the reactor and later on in the decommissioning phase.
2. WORKING LANGUAGEThe working language of the workshop will be English. No interpretation will be provided.
3. OBJECTIVESThe purpose of this workshop is to:
(a) review the recommendations that are presented in the relevant IAEA safety standards;
(b) introduce participants to best practices identified in existing operating programmes;
(c) provide exercises in how to apply these recommendations and best practices; and
(d) provide a forum for the participants to exchange experience as well as good practices from their respective countries.
4. PARTICIPATIONThis workshop is intended for individuals from research reactor operating organizations and personnel from regulatory bodies having responsibility for oversight of research reactor operations. Participants should be familiar with the safety considerations and issues involved in the operation and regulation of research reactors in their respective countries. Approximately 30 participants from 25 countries are expected to attend, along with representative(s) from the IAEA and guest lecturers.
5. WORKSHOP PROGRAMMEThe workshop will include lectures by IAEA staff and other lecturers, presentations by participants on their national operating programmes, and exercises and discussions in working groups. The following relevant IAEA documents and publications, together with the cumulative experience and expertise of the guest lecturers and participants, will form the basis for the workshop programme:
- Fundamental Safety Principles (IAEA Safety Standards Series No. SF-1, Vienna, 2006);
- Code of Conduct on the Safety of Research Reactors (IAEA, Vienna, 2006);
- Safety of Research Reactors (IAEA Safety Standards Series No. NS-R-4, Vienna, 2005);
- The Management System for Facilities and Activities (IAEA Safety Standards Series No. GSR- 3, Vienna, 2006);
- Application of the Management System for Facilities and Activities (IAEA Safety Standards Series No. GS-G-3.1, Vienna, 2006);
- The Management System for Nuclear Installations (IAEA Safety Standards Series No. GS-G- 3.5, Vienna, 2009);
- Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors (IAEA Safety Standards Series No. SSG-22, Vienna, 2012);
- The Operating Organization and the Recruitment, Training and Qualification of Personnel for Research Reactors (IAEA Safety Standards Series No. NS-G-4.5, Vienna, 2008);
- Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report (IAEA Safety Standards Series No. SSG-20, Vienna, 2012);
- Safety in the Utilization and Modification of Research Reactors (IAEA Safety Standards Series No. SSG-24, Vienna, 2012);
- Operational Limits and Conditions and Operating Procedures for Research Reactors (IAEA Safety Standards Series No. NS-G-4.4, Vienna, 2008);
- Maintenance, Periodic Testing and Inspection of Research Reactors (IAEA Safety Standards Series No. NS-G-4.2, Vienna, 2006);
- Ageing Management for Research Reactors (IAEA Safety Standards Series No. SSG-10, Vienna, 2010); and
- Decommissioning of Nuclear Power Plants and Research Reactors (IAEA Safety Standards Series No. WS-G-2.1, Vienna, 1999).
The information will be available soon.
Please check back.
- Abou Yehia
- L.1.2.Overview of IAEA SS and SRS for RRs.pdf
- L.2.1.Safety Stds for Mgmt of Operating Documents.pdf
- L.2.5.The Radiation Protection and Waste Management Programme.pdf
- L.2.6.Safety Analysis and Operational Limits and Conditions for RRs.pdf
- L.1.1.Safety Fundamentals.pdf
- L.2.2.Stds and Guidance for the Mgmt System.pdf
- L.1.3 Graded Approach for Research Reactors.pdf
- L.2.3 Maintenance Periodic Testing Inspection.pdf
- L.2.4 Ageing Management.pdf
- L.3.4 Maintenance of Operating Safety Documents in a Large Research Reactor.pdf
- Monday April 29, 2013
- Tuesday April 30, 2013
- Wednesday May 1, 2013
- Thursday May 2, 2013
- Friday May 3, 2013