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[en] Safeguards by Design (SBD): SBD is about establishing an early dialogue. The goal of this dialogue is to: • Foster an understanding of safeguards; • Take advantage of lessons learned; • Improve the effectiveness and efficiency of IAEA safeguards. Benefits will impact the designer, operator, State, and IAEA.
[en] IAEA SBD Guidance: • Basic principles document provides general information suitable for management, higher levels of nuclear regulatory bodies; • Facility-specific guidance focuses on issues of interest to the designer, vendor, operator; • Avoids use of safeguards jargon that is difficult to understand.
[en] According to NTR 2015, slightly more than half of the 438 operating reactors are more than 30 years old and about 14% of them are more than 40 years old. Although some may continue to operate for up to 60 years, many will be retired from service within the next two decades. This, combined with strong growth in nuclear construction in emerging nuclear power economies, particularly in Asia, suggests expanding room for next generation reactors in coming decades. There is a necessity to further strengthen the RD&D programs to prepare next generation reactor designs for commercial deployment.
[en] The introduction of advanced modeling and simulation practices over the last several decades has proven to produce better products, more quickly, and at the reduced cost. This computational experimentation has enabled the design and development of a variety of innovative products by reducing the need to build expensive prototypes, and by allowing rapid, comprehensive design studies across a wide range of products. Despite these successes, there are significant barriers to widespread adoption of these tools. This project aims to address several of these barriers.
[en] Under the U.S. DOE NEAMS program, the high-fidelity neutronics code system has been developed to support the multiphysics modeling and simulation capability named SHARP. The neutronics code system includes the high-fidelity neutronics code PROTEUS, the cross section library and preprocessing tools, the multigroup cross section generation code MC2-3, the in-house meshing generation tool, the perturbation and sensitivity analysis code PERSENT, and post-processing tools. The main objectives of the NEAMS neutronics activities in FY17 are to continue development of an advanced nodal solver in PROTEUS for use in nuclear reactor design and analysis projects, implement a simplified sub-channel based thermal-hydraulic (T/H) capability into PROTEUS to efficiently compute the thermal feedback, improve the performance of PROTEUS-MOCEX using numerical acceleration and code optimization, improve the cross section generation tools including MC2-3, and continue to perform verification and validation tests for PROTEUS.
[en] Qualitative Safety Features Review (QSR): • The Qualitative Safety Features Review is a “Checklist” based on principle of defense in depth. • QSR provides a systematic means of ensuring and documenting that the evolving Generation IV system’s design incorporates the desirable safety-related attributes and characteristics that are identified and discussed in the RSWG’s report. • Using a structured template, the QSR: – Provides a useful preparatory step to shape designers’ approaches to their work to help ensure that safety truly is “built in, not added-onto” since the early phases of the design of Generation IV systems. – Helps designer qualitatively assess safety-related strengths and weaknesses of the evolving design. – From earliest phases of design, helps influence design selecting or discarding options among the provision important to safety.
[en] Background: - Possible joined activities in area of VHTR have been considered since 2014; - The HTGR / VHTR Safety Design Requirements have been identified as the most beneficial area experience; - The OECD GSAR (Joint CNRA/CSNI Ad-hoc Group on the Safety of Advanced Reactors) selected only one system due to availability of limited resources; - SFRs (and unfortunately not VHTRs) as first excercise.
[en] The Lessons Learned Approach being followed at the Fast Flux Test Facility is to have domain experts in each subject area develop a short write-up or report on each Lesson Learned. Each lesson learned write-up is on the order of 4-6 pages. Longer reports can be developed as needed. Each Lessons Learned summary discusses the problem and the resolution method employed to address the problem, and also tries to capture the essential “tacit knowledge” associated with each topic in a focused manner. All lessons learned write-ups are supported by more detailed documents. For example, references of more detailed reports are generally included, where available. Topics are selected as those most likely to apply to future design or operating problems. This Lessons Learned Approach has been successful in capturing essential tacit knowledge about key events in FFTF history and providing a context for interpreting the existing data and references. (author)
[en] Conclusion: • Vendors provided a valuable demonstration of application of INPRO Methodology. • Vendors have important roles to (i) validate INPRO methodology, (ii) provide design information, (iii) help reduce assessor’s efforts in INPRO assessment of design specific areas. • For full scope NESA, assessors should work in close cooperation with vendors or with consultants with detailed design knowledge.