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[en] Introduction: The 2nd SDG on SSC provide detailed guidelines for SFR designers to support practical application of the SDC in design process to ensure the highest level of safety; The 2nd SDG is now under the international review process (IAEA and OECD/NEA's WGSAR); GIF SDC-TF received the comments from IAEA and OECD/NEA's WGSAR. Concluding remarks: GIF SDC-TF greatly appreciate important comments from IAEA and OECD/NEA's WGSAR; GIF SDC-TF will revise the 2nd SDG on SSC including terminology and configuration.
[en] The NRC is strategically transforming and modernizing to prepare for safe deployment of Avanced Reactors. NRC's implementation action plans are ensuring readiness in important strategic areas. Leveraging flexible review strategies with safety focus: Core Review Team Approach; Robust pre-application engagement program; Regulatory Review Roadmap. Enhancing access to information to improve transparency and increase engagement.
[en] The management system safety and control area (SCA) covers the framework that establishes the processes and programmes required to ensure an organization achieves its safety objectives, continuously monitors its performance against these objectives, and fosters a healthy safety culture. Performance objectives: There is an effective management system that integrates provisions to address all regulatory and other requirements to enable the licensee to achieve its safety objectives, continuously monitor its performance against those objectives, and maintain a healthy safety culture.
[en] FALCON Objective: Deployment of a LFR demonstrator having SMR-oriented features aimed at being a competitive option for the future Nuclear Power Plants (replacing the old generation NPPs facing retirement or conventional technologies based on fossil fuels), as well as longer-term potentialities to demonstrate that the LFR technology can meet the goals set out by GIF for Generation-IV reactors. Take-away: ALFRED will implement a staged approach to qualify the technical options for safe and competitive operation of a commercial fleet.; Following stages conditions will be reproduced in the ALFRED core through an in-pile section to qualify protective means and innovative materials for higher temperatures.; The demonstrator will serve as an intermediate step to address licensing challenges and lack of nuclear operational experience.; The ALFRED staged approach is the optimum trade-off between a reasonable time-to-market and the maximum attractiveness of the LFR technology, interms of safety, sustainability and competitiveness.; ALFRED is, per se, a prototype for a competitive commercial SMR based on LFR technology.
[en] In Indian Pressurised Heavy Water Reactors (IPHWRs) calandria tubes are rolled with end shield tube sheet at either ends with the help of a sandwich type joints. These calandria tubes are generally kept unchanged during en-masse replacement of pressure tubes and end-fittings; probably due to unavailability of technology for replacement of calandria tube. But in recent past, one irradiated calandria tube has been replaced successfully from one of the 220 MWe IPHWRs, with a new one, with the help of Calandria Tube Rolled Joint Detachment (CTRJD) system, developed by Reactor Engineering Division of Bhabha Atomic Research Centre (BARC). This paper gives brief description of CTRJD system, methodology of calandria tube rolled joint detachment, shop floor trials of the technique for optimisation of operating parameters, qualification trials at full length mock up facility and deployment at reactor site. (author)
[en] Conclusions: SDG-SSCs is a valuable exercise of consensus among designers at international level: useful for ''newcomers'' including TSOs and SAs; Few high ranked comments (16 over 134), but paragraph on containment design should be reframed; Many clarifications required - difficulty for TSO and SA to deal with design requirements; Objective to cover various concepts of SFRs makes SDG-SSCs sometimes difficult to apprehend (practical impact of requirements on safety).
[en] The government implements long term and systematic policies and strategies related to nuclear safety in accordance with the Nuclear Safety Act. For effective implementation of nuclear safety laws and various policies for safety regulation, a comprehensive mid term and long term nuclear safety plan is established and implemented every five years, along with a detailed implementation plan being established every year. The NSSC checks the implementation status every year in order to ensure its practical implementation. The Comprehensive Plan for Nuclear Safety is at the pinnacle of the national nuclear safety plan and establishes the mid term and long term policy direction for nuclear safety.
[en] A plant life management (PLiM) programme is an effective tool that allows an operator to manage ageing effects in structures, systems and components (SSCs) for long term operation of nuclear power plants. Such a programme helps facilitate decisions concerning when and how to repair, replace or modify SSCs in an economically optimized way, while assuring that the highest levels of safety are maintained. This publication is the proceedings of the fourth in a series of international conferences convened by the IAEA on nuclear power plant life management. The conference provided a forum for information exchange on national and international policies, as well as on regulatory practices, and for the demonstration of strategies, including their application in ageing management and PLiM programmes for operating and new nuclear power plants. The proceedings include the opening address, presentations of the keynote speakers, summaries of the individual technical sessions, and conclusions and recommendations of the chairperson of the conference.
[en] The main objectives of this meeting/workshop are to: Discuss the development of the draft GIF report provisionally entitled Safety Design Guidelines on Key Structures, Systems and Components; Discuss the review comments of external stakeholders on GIF report on Safety Design Guidelines on Key Structures, Systems and Components; Discuss the development of the Safety Design Criteria and Safety Design Guidelines for lead and lead-bismuth cooled fast reactors; and Share information on the implementation of SDG for SFRs and SDC for LFRs by the designers of the innovative LMFR concepts.
[en] Outline: - EU nuclear energy context: 106 nuclear reactors are in operation in 13 EU Member States; Nuclear energy provides about 25% of EU gross electricity generation, around 50% of EU low carbon electricity generation, and supports around 1 mil. jobs; In EU, each Member State can decide on the inclusion of nuclear power in its energy mix; 4 new reactors are under construction (FR, FI, Slovakia); About 20 reactors are in different stages of planning and preparation in 8 Member States (BG, CZ, EE, FI, HU, LT, PL, RO). - JRC Work Programme 2021 2022 related to the LMFR Safety. - Examples of the JRC technical activities in support to the LMFR Safety. - DG RTD activities in support to the LMFR Safety.