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[en] A thermal-hydraulic integral effect test program for the SMART (System-integrated Modular Advanced Reactor) design has been introduced, it is called VISTA-ITL. The VISTA-ITL is a small-scale integral effect test facility for the SMART design and it has the following characteristics: 1/2.77-height, 1/1310-volume and full pressure and temperature simulation of the SMART design. The VISTA-ITL will be used extensively to assess the safety and performance of the SMART design and to validate various thermal-hydraulic analysis codes such as the MARS and TASS/SMR. As a typical scenario of SBLOCA (Small-Break Loss of Coolant Accident) the safety injection line break accident has been analyzed with the MARS-KS code, to assess a thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility. The present similarity analysis ascertained the thermal-hydraulic similarity between the SMART design and the VISTA-ITL facility and provided a good insight into the unique features of the VISTA-ITL and the thermal-hydraulic characteristics of the SMART design as well. (authors)
[en] The paper presents the firs reports of the safety survey carried out at the Paks Nuclear Power Plant after the Fukushima accident. The seismic risk and resistance have been assessed as well as flooding risk and protection. (TRA)
[en] Significant cost and safety improvements can be realized in advanced liquid metal reactor (LMR) designs by emphasizing inherent or passive safety through crediting the beneficial reactivity feedbacks associated with core and structural movement. This passive safety approach was adopted for the Fast Flux Test Facility (FFTF), and an experimental program was conducted to characterize the structural reactivity feedback. Testing at the Rapsodie and EBR-II reactors had demonstrated the beneficial effect of reactivity feedback caused by changes in fuel temperature and core geometry mechanisms in a liquid metal fast reactor in a holistic sense. The FFTF passive safety testing program was developed to examine how specific design elements influenced dynamic reactivity feedback in response to a reactivity input and to demonstrate the scalability of reactivity feedback results from smaller cores like Rapsodie and EBR-II to reactor cores that were more prototypic in scale to reactors of current interest. The U.S. Department of Energy, Office of Nuclear Energy Advanced Reactor Technology program is in the process of preserving, protecting, securing, and placing in electronic format information and data from the FFTF, including the core configurations and data collected during the passive safety tests. Evaluation of these actual test data could provide insight to improve analytical methods which may be used to support future licensing applications for LMRs. (authors)
[en] Conclusions: • IAEA has mandate to establish nuclear security guidance and to support States, on request, in its application; • Framework is in place: → High level guidance published; → Structures and processes established. • Priority is to complete comprehensive suite of guidance: → For use by States; • As basis for Agency’s other activities.
[en] Very small special purpose reactors (SPRs) are under consideration by various entities for remote installations and communities. This type of plug-and-go resource requires inherently positive safety attributes and sound design. Such reactors may be transportable with fresh fuel to serve as a complete power “battery” and they may even be transportable on short notice after initial use. SPRs could eliminate costly and in some cases dangerous fossil fuel deliveries. Small passively safe reactors could be operated remotely by an offsite operations crew. While use cases for such reactors are currently under development, advanced manufacturing processes should be considered to support reactor economics.
[en] Workshop Outcomes: • Representatives of all six SSCs gained a much fuller understanding of the ISAM, its purposes, and its application. • Overall, all six SSC representatives expressed strong support for ISAM and endorsed its value and practicality: – Clear consensus to begin using it on a trial basis; – At least two development teams are already doing so. • The only significant concern expressed by the SSCs related to resource requirements and expertise needed to apply the ISAM. • Draft ISAM document includes comments and perspectives discussed at the workshop.
[en] The authors highlight the necessity for nuclear reactors to be intrinsically safe, it means to be safe without the intervention of the reactor control-command system. This intrinsic safety is obtained by dynamic counter-reactions. It is important that these counter-reactions do not change the nature of the physico-chemical phenomena that contribute to them. It is also important to consider in what circumstances these counter-reactions stay linear because the linearity allows the decoupling of the physical phenomena involved and an easier solving of the corresponding equations
[en] The paper presents the firs reports of the safety survey carried out at the Paks Nuclear Power Plant after the Fukushima accident. The events of loss of electric supply, of long lasting loss of final heat damp, of radioactive emission following a serious reactor accident and of radiation of extreme intensity are analyzed. (TRA)