• Aucun résultat trouvé

This section provides the summary of plenary presentations made by China, France, India, Japan, Republic of Korea, the Russian Federation, European Commission, Generation IV International Forum and International Atomic Energy Agency. The Russian Federation as a host country delivered an additional first keynote speech.

Full unedited keynote contributions are provided after the short summary of the plenary sessions.

3.1. RUSSIAN FEDERATION

E. Adamov, Former Head of the Russian Atomic Energy Ministry (ROSATOM), presented the results obtained during the five years of the PRORYV Project, which confirmed the technological feasibility of its fundamental principles and made it possible to proceed to the practical development stage and to a new nuclear technological platform. The implementation of the developed design, engineering and processing solutions and the realization of the planned Pilot Demonstration Energy Complex R&D programme (phase one start-up scheduled for 2020) made it possible to anticipate, with confidence, the development of a prototypical industrial energy complex capable of operating within a two-component nuclear power scheme by 2030. In this regard, a prototype of a next generation nuclear reactor is to be built at the site of Joint Stock Company Siberian Chemical Plant by the joint efforts of ROSATOM experts and Russian Academy of Science universities and institutes.

3.2. CHINA

H. Yu, Deputy Director responsible for International Cooperation, China Institute of Atomic Energy (CIAE), explained that China is developing nuclear energy with a capacity of about 30 GW, with 35 NPPs in operation and another 19 under construction, with the target to reach 58 GW by 2020 and about 400-500 GW by 2050, although the average utilization of nuclear power plants in China has declined for the last three years. The reasons behind this decline are that China's economy is in a period of adjustment, with cheaper coal prices and an abundance of water and hydroelectric power. Several new generation nuclear energy systems are currently under study in China with the focus on sustainable nuclear fuel cycles, that save uranium resource and reduce the burden of generated radioactive waste, to meet the future demands.

3.3. FRANCE

S. Pivet, Deputy Head of the Nuclear Energy Division at the French Alternative Energies and Atomic Energy Commission (CEA), explained that nuclear energy will remain one of the pillars of the future French low carbon energy mix. The closed fuel cycle associated with fast neutron reactors will lead to drastic improvement in uranium resources management and important reduction in footprint and radiotoxicity of the final wastes. The French programme on Gen IV is based on the “Accompagnement Spécifique des Travaux de Recherches et d’Innovation Défense” (specific support for defence research projects and innovation) programme, with the basic design phase ongoing for the period 2016–2019. The schedule and organization of the next phases are under preparation by the French government and industrial partners. At the same time, France is conducting an active survey on other Gen IV fast and thermal neutrons systems.

3.4. INDIA

A. Bhaduri, Director of the Indira Gandhi Centre for Atomic Research (IGCAR), summarized the details of the Indian fast reactor programme and discussed its status and R&D achievements. The fast reactor programme in India has several aspects. The construction of the Fast Breeder Test Reactor (FBTR) allowed comprehensive experience in construction and operation, and in the provision of material irradiation data, including for reactor and energy conversion systems. The Prototype Fast Breeder Reactor (PFBR) is intended for technical and economic demonstration of the system. The fast reactor programme will provide additional R&D opportunities in design and fuel reprocessing, as well as in improved economics and enhanced safety. The Indian fast reactor programme is essential for the security and sustainability of energy in India. Experience from FBTR operation and PFBR design, manufacture, construction and safety review have improved confidence in fast reactor deployment in a closed fuel cycle mode and with no technological constraints envisaged. In striving for a higher growth rate, R&D on metal fuel with high breeding potential along with associated fuel cycle technologies is in progress. India continues to place a strong emphasis on R&D directed towards building up a substantial fast reactor programme in the future.

3.5. JAPAN

Y. Sagayama, Japan Atomic Energy Agency (JAEA) announced that “The Fourth Strategic Energy Plan” of Japan was approved by the Cabinet in April 2014: it states that nuclear energy is an important baseload power source as a low carbon and quasi-domestic source even after the TEPCO Fukushima Dai-ichi accident. Japan will promote nuclear closed fuel cycle in terms of the efficient use of resources and volume reduction. Mitigation of degree of harmfulness of high-level radioactive waste carries out fast reactor cycle R&D for the commercialization, taking advantage of international cooperation.

3.6. REPUBLIC OF KOREA

J. Yoo, Technical Director of the Sodium Cooled Fast Reactor Development Agency(SFRA), Korea Atomic Energy Research Institute(KAERI) informed that the Korea Atomic Energy Commission authorized the R&D action plan for the development of the advanced sodium cooled fast reactor (SFR) and the pyro-processing technologies to provide a consistent direction to long term R&D activities in December 2008. This long term advanced SFR R&D plan was revised by Korea Atomic Energy Promotion Council (KAEPC) in November 2011 in order to refine the plan and to consider the available budget for SFRs. The revised milestones include the specific design of a prototype SFR by 2017, specific design approval by 2020, and construction of a prototype Gen IV SFR (PGSFR) by 2028. The prototype SFR programme includes the overall system engineering for SFR system design and optimization, integral V&V tests, and major components development. Based upon the experiences gained during the development of the conceptual designs for Korea Advanced Liquid Metal Reactor (KALIMER), the conceptual design of PGSFR had been carried out in 2012 following by performing a preliminary design since 2013. The first phase of the development of PGSFR had been completed at the end of February 2016 and the second design phase at the end of 2016.

All the design concepts of systems, structures and components (SSCs) were determined and incorporated into the Preliminary Safety Information Document (PSID), which includes basic design requirements, system and component descriptions, and the results of safety analysis for

the representative accident scenarios. The PSID will be a base material for a pre-review of the PGSFR safety. The target of the second phase of PGSFR design was to prepare a Specific Design Safety Analysis Report (SDSAR) by the end of 2017. The SDSAR is equivalent to the conventional Preliminary Safety Analysis Report (PSAR) but without the specific site information of the plant. To support the design, various R&D activities are being performed in parallel with design activities, including V&Vs of design codes and system performance tests.

3.7. RUSSIAN FEDERATION

A. Tuzov, Director of the Research Institute of Atomic Reactors (RIAR), delivered a presentation on the Russian Federation’s research and pilot fast reactors, which are considered as the basis for the development of the commercial reactor technologies. Research reactors have demonstrated their role as the crucial element for the consistent and coherent development of fast reactor technology. Sodium fast reactor technology is currently the only mature concept implemented on an industrial scale. The lessons learned confirm the appropriateness of the step by step approach, on the road from reactor test facilities to prototypes and, ultimately, commercially feasible fast reactors. The viability of the whole fast reactor technology clearly depends on ensuring the closure of the fuel cycle. Commercially viable long term solutions will require full usage of existing research reactor infrastructure. The ageing of the sophisticated infrastructure should demand consolidation of stakeholder efforts, also at the international level. Considering the RIAR research infrastructure and the personnel qualifications at the institute, as well as the many years of experience gained in the development and operation of fast reactors and related fuel cycle facilities, RIAR fulfills its role admirably.

3.8. EUROPEAN COMMISSION (EC)

J-P. Glatz, Head of Nuclear Safety of the JRC Directorate for Nuclear Safety and Security of the European Commission (EC), discussed contributions for the development of fast reactor systems based on platforms, initiatives and alliances created to facilitate distribution of the R&D resources. The activities are organized in multi annual framework programmes (at present Horizon 2020 Project) with collaboration projects co-financed by Directorate General for Research and Innovation (DG RTD) and with direct research carried out in the Joint Research Center (JRC), new EC Directorate for Nuclear Safety and Security. These programmes focus mainly on the reactor itself (reference: SFR, alternatives: LFR and GFR), as well as fuels, fuel cycles and related materials. Furthermore, JRC is the implementing agent for European Atomic Energy Community (EURATOM) in GIF and in this capacity contributes to all six GIF reactor conceptual designs selected for further R&D, taskforces and cross-cutting working groups.

3.9. GENERATION IV INTERNATIONAL FORUM (GIF)

F. Gauché, Head of Generation IV International Forum (GIF), introduced and gave details of the recent GIF activities over the past four years. New members have joined GIF since FR13 conference in Paris. Detailed descriptions of six GEN IV conceptual reactor designs were presented, compared and discussed. SFRs remain in focus to GIF members and also attract the interest of the private sector. Recently, GIF achieved significant success in developing Safety Design Criteria (SDC) and Safety Design Guidelines (SDG) for SFRs. The recent GIF reports on SDC and SDG became a topic for the panel discussion at the FR17 conference. Other reactor designs, such as LFR, MSR and GFR are also studied under the GIF framework. GIF established an education and training task force to promote GEN IV systems and related topics.

3.10. OECD/NUCLEAR ENERGY AGENCY (NEA)

T. Ivanova, Head of Division of Nuclear Science, Nuclear Energy Agency of Organization for Economic Cooperation and Development (OECD/NEA), highlighted the commitment of the NEA to support advances in the fundamental science and technology that underpin fast reactors, including nuclear data, integral experiments, transient benchmarking, materials science and fuel cycle scenarios and technology, serving as a forum for exchanging information and promoting collaborative activities. As an example, the group on the safety of advanced reactors (GSAR) has been recently established to discuss regulatory and safety issues related to Gen IV designs and, during the workshop on reactor systems and future energy market needs, the future of nuclear baseload was extensively debated.

3.11. INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA)/ INTERNATIONAL PROJECT ON INNOVATIVE NUCLEAR REACTORS AND FUEL CYCLES (INPRO)

J. Philips, Section Head of the IAEA International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), covered the main activities of INPRO in the areas of nuclear energy system sustainability assessment and in whole system scenario analysis in support of long term planning for sustainable development of nuclear energy. The special focus of this presentation was on the projects that directly involve fast reactors, related fuel cycles and the potential for international cooperation through trade and R&D collaboration. In particular, projects include the application of the INPRO methodology for assessment of the sustainability of specific sodium fast reactor designs in China, India and the Russian Federation in areas of safety and economics. In addition, the whole system scenario analysis of the regional and global nuclear energy systems involving fast reactors, related fuel cycles and trade-in related nuclear products and services between cooperating countries were also discussed. Services provided to the Member States in the use of the INPRO methodology and scenario analysis tools were also described.

4. PLENARY SESSION - KEYNOTE PAPERS