Outlines of IAEA Activities in Support of Research and Innovation in the Field of Nuclear Energy

Transcription

1 High Level Workshop Launching the NEA NI2050 OECD, Paris, 7-8 July 2015 Outlines of Activities in Support of Research and Innovation in the Field of Nuclear Energy Stefano Monti Head of Nuclear Power Technology Development Section Department of Nuclear Energy International Atomic Energy Agency

2 The Coordinated Research Activities (CRAs) International Atomic Energy Agency

3 CRA Objectives Contributing to the objectives of the Agency Projects Promoting and coordinating cooperative research done by Member States institutions in all peaceful use areas within the Department of: Nuclear Energy, Nuclear Safety and Security, Nuclear Science and Applications Percentage of funds obligated by Major Programme in % 17% Nuclear Power, Fuel Cycle and Nuclear Science 73% Nuclear Techniques for Development and Environmental Protection Nuclear Safety and Security 3

4 CRA Objectives Providing opportunities to scientists in developing and developed countries to work together to solve a problem of common interest. Developed Countries % Developing Countries % 4

5 CRAs at a Glance in coordinated research projects (CRPs) and about 1900 research institutions involved in contracts/ agreements Average duration of a CRP: 5 years The awarded around 6.8 million for its Coordinated Research Activities in 2014 Average award per contracting institution and per year was about Research Coordination Meetings (RCMs) 5

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7 Publications added to the completed CRPs 7

8 CRP results/outputs Networks established Reports and Databases Scientific and Technical Publications Proven techniques tested and ready to be transferred CRPs leading to TC Projects Coordinated Research Project Technical Cooperation Individual Research in Labs Distribution to Several Labs: Testing and Validation of the Research Results of the Research published. Networking and Proven technologies ready to be transferred Technical Cooperation Project to assist in the transfer of technology Dissemination of the Technology to Member States and Socio-economic Impact 8

9 CRPs in the Area of Nuclear Energy (1/2) Nuclear Power Plants in operation: Qualification and monitoring of aged low voltage cables Piping wall thinning due to erosion-corrosion in NPPs Application of wireless technologies in NPPs and I&C systems Advanced reactors: WCR (e.g. CFD, SCWR T/H, creep in HWR tubes) HTGR (e.g. uncertainty analysis, graphite creep behaviour) FR (e.g. PHENIX, MONJU, BN-600, EBR-II, PFBR, NAPRO) SMR Non-electrical applications: Low temperature desalination systems Cogeneration involving nuclear energy Nuclear hydrogen production 9

10 CRPs in the Area of Nuclear Energy (2/2) Fuel cycles and Waste Technology Front-end: Geochemical and mineralogical characterization of U/Th deposits Fuel: Th-based fuels, fuel modelling in accident conditions, LWR accident tolerant fuel Back-end: management of severely damaged spent fuel and corium, spent fuel performance assessment, processing technologies for high level waste formulation of matrices and characterization of waste forms Research Reactors Back-end of RR fuel cycle Low enriched U-Mo fuel Producing Mo-99 using LEU Benchmark on fuel burn-up and material activation 10

11 Other R&I Activities / Initiatives 11

12 INPRO (1/2) Nuclear Energy System Modeling and Analysis Dynamic system models of nuclear energy Key indicators for analysis of innovative NES options Roadmaps for transition to innovative NES and FC Innovations in Nuclear Energy System CP on transportable factory fuelled SMR CP on waste arising from innovative reactors and fuel cycles CP on analysis of innovative fuels and fuel cycles Good practices for international collaboration on innovative technologies CP on cooperative approaches to nuclear fuel cycle back end CP on prevention of severe accidents in advanced reactors 12

13 INPRO (2/2) Nuclear Energy System Sustainability Methodology to perform sustainability assessments of NES Continuous improvement of the INPRO Methodology (9 volumes) Member State Dialogue on NES Sustainability and Innovation Dialogue Forums on NE sustainability and innovation topics of interest of new comer countries, technology users and technology holder/developers Interfaces between INPRO and other international organizations promoting development of sustainable innovative nuclear energy technologies and institutional frameworks (GIF, IFNEC, NEA, etc.) 13

14 Databases, Catalogues & Tool-kits ARIS database: design information of advanced nuclear reactors TERPRO database: physical properties of materials associated with nuclear reactors Compendium of research reactors for development of materials and fuels for innovative nuclear energy systems Material properties database for irradiated core structural components for ageing research reactors Compendium of experimental facilities in support of liquid metalcooled fast neutron systems Database of historical irradiated nuclear graphite PC-based principle-based simulators of several different NPPs Toolkits for non-electrical applications Toolkit of severe accident management development guideline 14

15 Nuclear Safety (1/2) Directions based on new requirements of Safety Standards Applicability of current Safety Standards to innovative designs e.g. physical variables used for LWRs may not be applicable to innovative designs Provision of large number of countries needs Wide acceptability of international consensus Safety Standards 15

16 Nuclear Safety (2/2) Examples of specific topical areas requiring focus Human factors Digital I&C Fuel performance Determination of postulated initiating events and extended conditions Applicability of current codes and standards e.g. standards for refractory materials 16

17 Nuclear Safety Action Plan Safety Assessments Peer Reviews Emergency Preparedness and Response 4. National Regulatory Bodies Operating Organizations Safety Standards International Legal Framework Member States Embarking on Nuclear Power Capacity Building Protection from Ionizing Radiation Communication Research & Development Research and Development: key area for continuous improvement on Nuclear Safety Cross-cutting area carried out throughout the NSAP

18 International Experts Meeting on Strengthening Research and Development Effectiveness in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant IEM8 Co-organized by NE/NS in cooperation with OECD/NEA Date: February 2015 Venue: Headquarters 150 participants from 35 MSs and 5 international organizations Objectives: exchange information and experience related to R&D work undertaken assist Member States in planning and implementing R&D activities 18

19 IEM8 Topics of Opening and Technical Sessions OS: International perspectives on nuclear safety R&D TS-0: R&D strategies after the Fukushima accident TS-1: Common cause failures due to external and internal events TS-2: Technologies to prevent/ mitigate severe accidents TS-3: Severe accident analysis TS-4: Emergency preparedness and response (EPR) TS-5: Post-accident recovery 19

20 Outputs & Next Steps Outputs: Presentations/Posters and Chairpersons Summary Meeting report summarizing the current status of R&D activities and identifying future R&D areas Next Steps: Publish IEM8 Report Technical Meetings to discuss specific topics for international collaboration Workshops to share information obtained in IEM8 and TMs Implementation of recommendations (e,g, new CRPs and other initiatives) under internal discussion 20

21 Other Thank you for your attention!