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Passerini, S.

Publications and source records attributed to Passerini, S..

Electrochemical investigations of high-voltage Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 cathode for sodium-ion batteries

In this work, the electrochemical properties of carbon and reduced graphene-coated Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 materials have been evaluated as high-voltage positive electrodes for sodium-ion batteries. Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 exhibits the highest Ni 3+ /Ni 2+ redox potential of 4.8 V vs. Na + /Na with a theoretical capacity of 127 mAh g -1 . Here, we report on the synthesis and characterizations of Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 -reduced graphene oxide and Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 -carbon composites. The high-voltage dimethyl carbonate–based electrolyte has been chosen to explore the electrochemical properties of Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 as a cathode. Carbon-coated Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 composite electrode delivers a stable discharge capacity of 51 mAh g -1 at 0.1 C rate for 40 cycles which corresponds to a reversible intercalation/de-intercalation of 1.3 sodium ions. The structural deformation has been observed during the charge–discharge process beyond the removal of 1.3 Na + ions and has been confirmed by in situ PXRD measurements. The present results provide a guideline to improve the performances of the high-voltage Na 4 Ni 3 (PO 4 ) 2 P 2 O 7 material for the next generation sodium-ion batteries.

25 ENERGY STORAGE↗

Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment

Beginning in 2015, a project was initiated to update and modernize the probabilistic safety assessment (PSA) of the GE-Hitachi PRISM sodium fast reactor. This project is a collaboration between GE-Hitachi and Argonne National Laboratory (Argonne), and funded in part by the U.S. Department of Energy. Specifically, the role of Argonne is to assess the reliability of passive safety systems, complete a mechanistic source term calculation, and provide component reliability estimates. The assessment of passive system reliability focused on the performance of the Reactor Vessel Auxiliary Cooling System (RVACS) and the inherent reactivity feedback mechanisms of the metal fuel core. The mechanistic source term assessment attempted to provide a sequence specific source term evaluation to quantify offsite consequences. Lastly, the reliability assessment focused on components specific to the sodium fast reactor, including electromagnetic pumps, intermediate heat exchangers, the steam generator, and sodium valves and piping.

Passive Systems↗

Overview of simulation and control tools for extended operability of nuclear reactors - 183

The increasing penetration of Renewable Energy Sources (RES) requires the current power grid to be suitably improved. Because of the unsteady nature of RES, as long as energy storage facilities are not deployed and commercialized, an increased effort for the frequency regulation in order to ensure high reliability and performance is necessary. In such a scenario, nuclear units (traditionally deployed as baseload generating units) will be required to cooperate with intermittent RES-based power plants. Therefore, new reactors will need larger operational flexibility with respect to the capabilities of the currently operated units. Over the last few years, a comprehensive research program oriented at developing a suite of simulation tools and control system development capabilities was pursued at Argonne National Laboratory. In addition to the study of advanced reactor concepts (e.g. metal-fueled Sodium-cooled Fast Reactors) and technological innovations (such as S-CO{sub 2} Energy Conversion Cycles), new control approaches were developed to improve the operability of nuclear power plants. In particular, Model-based Predictive Control algorithm for Multiple Input Multiple Output control strategies and set-point definition algorithm based on Reference Governor were studied and applied to specific scenarios, providing with a range of novel capabilities able to meet the expected greater sets of requirements mentioned above. In this work, an overview of such tools and case studies is presented with particular focus on their impact on operability and economic competitiveness of nuclear energy. (authors)

22 GENERAL STUDIES OF NUCLEAR REACTORS↗