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[en] Design Extension Condition (DEC): • Severe Accident: [SA] – Important due to the characteristics of SFR. – Prevention of the occurrences & Mitigation of the consequences shall be required. – Consequences of severe reactivity insertion, which might occur in the course of the CDA, shall be accommodated. • Built-in measures against the CDA: – On the designs of fuel and assemblies, reactor core, core support structure, shutdown system, coolant system and/or containment system, – By effectively utilization of passive mechanisms.
[en] Five Key Topics: 1. Overview of safety approach in the different countries. 2. Approaches to resolve safety issues related to basic safety characteristics (reactivity feedbacks, passive & inherent safety, prevention/mitigation of CDA). 3. Approaches to resolve safety issues related to Na as a coolant (Na boiling, fires, leak detection, Na-H2O interaction, SGTR). 4. Safety implication in the light of Fukushima accident (severe accident, external events, post severe accident management). 5. Design concepts for innovative SFR achieving enhanced safety.
[en] Discussions on SFR safety features: • Focuses on five key viewpoints, based on the Japanese government report to the IAEA: – Strengthen preventive measures against a severe accident; – Enhancement of measures against severe accidents; – Enhancement of nuclear emergency response; – Reinforcement of safety infrastructure; – Raise awareness of safety culture; • SFR safety features in comparison with LWR: – External Events: • Impacts common to all the NPPs, and differences in consequences. – Differences: e.g. Decay heat removal systems: • Possibility of natural circulation with passive, • Not requiring electrical power, • Diversity of final heat sink – ambient air.
[en] Summary: • Two promising SCWR concepts have been worked out and published; pressure tube concept still under development. • Technology development ongoing. • A fuel qualification test is being designed and licensed. • Successful collaboration between GIF and INPRO is demonstrated in joint meetings and conferences.
[en] Objectives of PR&PP Working Group: • Facilitate introduction of safeguards and security features into the design process at the earliest possible stage of concept development; • Assure that conclusions of PR&PP assessments are an aid to informing decisions by policy makers in areas involving safety, economics, sustainability, and related institutional and legal issues.
[en] Metal fuel development: • Fabrication and Testing of pins in FBTR. • FBTR core conversion as predominantly metallic fuel. • Construction of an experimental 320 MWt test reactor with metallic fuel core for testing of power reactor full-scale metal fuel subassemblies. • A pyroprocess plant for treating the spent metal fuels from FBTR will be set up and commissioned in 2020. Preliminary physics design of 320 MWt experimental metal core completed.
[en] INPRO and the Generation IV International Forum (GIF) have been collaborating based on the synergies originated by their programmes of activities, which common goal is to contribute to the sustainable development of nuclear energy in the 21st century. Regular interface meetings have been held since 2003. The objectives of the 6th GIF-INPRO/IAEA Interface meeting were to: • Share information on the progress status and future plans of activities related to technology innovation of nuclear energy systems; • Monitor the progress in cooperation agreed during the last interface meeting; • Continue exploring areas of potential cooperation, identifying action items and establishing priorities for further consideration. • Discuss the results of, and future actions resulting from, the 2nd Joint GIF-IAEA/INPRO Workshop on Safety Aspects of Sodium-Cooled Fast Reactors (30 November–1 December 2011). The meeting also covered updates on reactor safety assessments based on lessons learned from the Fukushima nuclear accident.
[en] Overview of the VHTR fuels and fuel cycle project; the VHTR materials project; the VHTR Hydrogen Production Project; the VHTR Computational Methods, Validation and Benchmarking Project; and of the VHTR System Arrangement Outlook.
[en] Generic Reactor Safety Review Results: Provision of a review by a corps of knowledgeable internal and external reviewers, including: Insight into the application and implementation of IAEA Safety Requirements for new reactor designs; Clear observations and comments on whether vendor safety cases are complete and in line with IAEA Safety Requirements; Carefully screened review results and observations which assist MS in attaining the highest levels of reactor design safety and compliance with IAEA Safety Requirements; A complete safety assessment package containing review sheets for each requirement and for each reactor design being considered.
[en] An important new priority has been added since Fukushima, and that is to ensure a strong contribution from the Nuclear Energy Department to the implementation of the Agency’s Action Plan on Nuclear Safety. Our Department has substantial expertise and we have much to contribute. It is my strong belief that safety depends directly on technology, and next generation reactors and the corresponding fuel cycle facilities will be designed to be as safe or safer and more stable than technology available today. Next on the priority list is support for operating reactors, expanding programmes, new programmes, uranium mining and the back-end of the nuclear fuel cycle. Here my goals are to expand our services and products in all areas. Another priority is increasing knowledge and awareness about nuclear waste. The goals are to increase public awareness about existing experience in safe and efficient nuclear waste management and promote good practices in this area. Furthermore, we want to reinforce Agency efforts to create a level playing field through a strong role in international discussions and studies on climate change, sustainable development and financing, as part of the UN Secretary General’s initiative “Sustainable Energy for All”. Concerning research reactors, the priorities are to support conversion from high enriched uranium to low enriched uranium, help improve utilization and aging management, the production of medical radioisotopes, and publish milestones for a country’s first research reactor. And last but not least are advanced technology and INPRO. Here the priorities are maintaining a strong exchange of information on advanced technologies, particularly with newcomer countries, and strengthening INPRO activities on Nuclear Energy System Assessments, a global vision for sustainability, the Dialogue Forum and institutional and technological innovations.