Call for Papers

Oral papers and poster presentations are invited on

• All key areas of the nuclear fuel cycle of Research Reactors - Fissile material supply. Fresh fuel and targets: Origin and status, qualification, fabrication. Technical aspects of fuel in-core management and safety. Fresh and spent fuel transportation. Fuel and reactor licensing. Spent fuel storage, corrosion and degradation. Fuel back-end management.
• Innovative methods in research reactor analysis and design – Development and application of advanced computational methods and tools for research reactors physics, safety and fuel management: Neutronics Calculations and Experiments, Methods and Tools for Research Reactor Core Analysis and Design, Fuel Cycle Physics (including Actinides transmutation and proliferation reduction issues), Nuclear Safety Assessment Methods and Improvements for Research Reactors.
• Utilization of Research Reactors – Preparation and implementation of strategic and business plans, deployment of additional research reactor applications and marketing of research reactor services. Utilization experience and good practices, especially from well utilized research reactors. Stories of success in improving research reactor sustainability. Utilization of research reactors for research, development, education, training and industrial applications. Articulation and operation of research reactors networks, coalitions and centres of excellence. Experiences of successful application of strategic planning in the transition from full government support to total or partial facility self-sustainability and self-reliance; Research Reactor Support for Innovative Nuclear Power Reactors and Fuel Cycles: Research reactor utilization in support of international initiatives on innovative nuclear power reactors and fuel cycles, including inter alia the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), Generation IV International Forum (GIF), the US DOE Advanced Fuel Cycle Initiative and the US Global Nuclear Energy Partnership (GNEP). Examples of advanced research carried out in research reactors in support of these multilateral undertakings. Identification of research reactor capabilities needed by the international initiatives on innovative nuclear power reactors and fuel cycles. Identification of challenges, constraints and capability gaps potentially limiting research reactor’s ability to provide necessary support.
• Research Reactor Support for Innovative Nuclear Power Reactors and Fuel Cycles - Research reactor utilization in support of international initiatives on innovative nuclear power reactors and fuel cycles, including inter alia the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), Generation IV International Forum (GIF), the US DOE Advanced Fuel Cycle Initiative and the US Global Nuclear Energy Partnership (GNEP). Examples of advanced research carried out in research reactors in support of these multilateral undertakings. Identification of research reactor capabilities needed by the international initiatives on innovative nuclear power reactors and fuel cycles. Identification of challenges, constraints and capability gaps potentially limiting research reactor’s ability to provide necessary support.

• New Research Reactor Projects – National and regional plans for new research reactors. Lessons learned from building and operating new research reactors. Role of research reactors in developing nuclear competence to implement nuclear power programmes in a medium to long term perspective. Research reactor capacity needed to meet the future demand for radioisotopes for medicine and industry. Development of national and regional infrastructure necessary to implement new research reactor projects, including inter alia organization and management, uses and applications, funding and financing, stakeholder involvement, legislative framework, regulatory framework, nuclear safety, environmental protection, security and physical protection, safeguards and human resources.

• Research Reactor Operation and Maintenance and Ageing – Plant material condition control, managing issues at either end of the facility 'bathtub curve' (commissioning, early operation and end of life/ageing related issues), maintenance assessments and risk informed maintenance programmes, management systems, configuration management, procedure utilisation, communications and work control, design review and control, human resource development and training programmes, regulatory interface, public relations, management improvement programmes and performance monitoring

·         2010 TRIGA User Meeting - The 2010 TRIGA User Meeting will be organised as an embedded meeting within RRFM 2010. If you would like to actively participate in the 2010 TRIGA User Meeting by giving an oral presentation please upload a short abstract.

Conference Secretariat:

European Nuclear Society

65 Rue Belliard

1040 Brussels, Belgium

Tel. +32 2 505 30 54
Fax +32 2 505 39 02

rrfm2010@euronuclear.org