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[en] Concluding remarks: • The Interim Safety Design Criteria (SDC) report is provided to IAEA, being ready to start technical interaction with IAEA. • The updated SDC report will be delivered to next GIF PG meeting in May with the incorporation of the feedback from the joint GIF/IAEA SFR SDC workshop. • The SDC report would be disseminated and utilized for SFR design at international level. • Safety improvement comes from continuous efforts for updating safety designs: – It is enhanced by the new safety technology and recent knowledge related to the operation experiences and R&D outcomes; – In this sense, the SDC will be updated with the times as necessary, by including constructive feedbacks from all the international technical entities including regulatory bodies.
[en] • GIF prospective interest: – Application of INPRO methodology may help to reveal potential gaps in R&D program and to close these gaps. – NESA study may be useful for future marketing of the reactor design. • INPRO prospective interest: – Feedback from the assessment of systems based on innovative reactors.
[en] Vision: Programme Development: Four INPRO projects - 1. Long-range national nuclear energy strategies: supporting Member States' nuclear sustainability assessments, strategic planning and decision making, using the INPRO methodology; 2. Global sustainable nuclear energy scenarios: system studies of long-term development and deployment of sustainable nuclear energy systems; 3. Technical and institutional innovations: facilitating collaboration on selected technological subjects and changes in institutional arrangements to facilitate innovation; and 4. INPRO Dialogue Forum on Global Nuclear Energy Sustainability: fosters information exchange on key issues of mutual interest between nuclear technology developers, users, and other stakeholders.
[en] During the last two days, we had the third GIF-IAEA Workshop on safety of sodium-cooled fast reactors (SFR). This time, we've had intensive discussion on the safety design criteria. I hope the safety criteria of GIF would be developed into the criteria of the IAEA and be applied internationally in the future.
[en] Brief overview of: the current status and activities of LFR PSSC; the European Lead-cooled Fast Reactor ELFR; the BREST-OD-300 Lead-cooled Reactor; the Small Secure Transportable Autonomous Reactor (SSTAR); and the EC Next Step Update of Strategic European Documents.
[en] The dissemination of the GIF-RSWG and INPRO methodologies was at the core of the workshop held in Petten 28-29th March where members of the SARGENIV consortium had the opportunity to exchange opinions and thoughts with key experts from INPRO and GIF-RSWG. The information gathered helped to gain better insights of the safety approaches in terms of DiD implementation and deterministic assessment and of new and future perspectives more oriented towards a probabilistic assessment and risk-informed approach. INPRO and QSR have been identified in the SARGENIV harmonized safety assessment practices as the tools to verify the compliance of the design with the safety requirements. A specific action is suggested to interact with the IAEA/INPRO team in order to discuss the opportunities for mutual improvements.
[en] The close cooperation of INPRO with the three GIF methodology working groups (proliferation resistance and physical protection, risk and safety, and economic modeling) has been very productive and should continue. In the future, GIF will continue to focus its efforts on facilitating advanced reactor R&D cooperation among our members. As part of the GIF vision, I am open to hearing from IAEA about any suggestions on how INPRO and GIF can strengthen our relationship to support mutual objectives.
[en] The continuation of this dialogue and cooperation between the Generation IV International Forum and INPRO, and the broader IAEA nuclear energy technology community, helps create an important link between the IAEA’s diverse efforts to assist Member States and supports an important international collaboration among several leading nuclear technology developing nations. The R&D efforts moving forward under Generation IV are pushing the forefront of reactor technology.
[en] Summary: - Various collaborative activities are being conducted in the areas of Advanced Fuels, Transmutation of MAs, Component Design and Balance-of-Plant, and Safety and Operation; - Efforts were made to conduct R&D activities consistent with key priority objectives; - Project Arrangements are now being amended through evaluation of achievements, consideration of changes in national programs, and participation of new members; - There has been limited application of GIF methodologies; - Challenging technology gaps were identified and R&D tasks have been developed by PMBs.
[en] PROSA - Ultimate goal: • Make assessment of Proliferation Resistance simpler, less time consuming. • Provide recommendations to revise INPRO Manual on Proliferation Resistance (TECDOC/1575, rev. 1, Volume 5 ). • Use only the depth of analysis necessary to address the assessor’s needs (two-dimensional phased assessment): – Facility level – comparative assessment, safeguardability assessment, diversion path analysis; – NES level – diversion path analysis; • State level – evaluate completeness of legal and regulatory undertakings and their implications at NES and facility levels; – “Self assessment” or “assessment by others” affects assessment philosophy and purpose.