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25. Preliminary study on oxidation of nuclear grade graphite

Author

Mazzi, Martina, Chebac, Riccardo, Campi, Fabrizio, Ricotti, Marco, Poskas, Gintautas, Derudi, Marco, and Porta, Alessandro

Subjects
Thermal oxidation, graphite, risk assessment, decommissioning of nuclear reactors
Published
2022

29. Characterization of Removable Coatings for Graphite-moderated Nuclear Reactors Decommissioning.

Author

Mazzi, Martina, Chebac, Riccardo, Campi, Fabrizio, Ricotti, Marco, Porta, Alessandro, and Derudi, Marco

Subjects
GRAPHITE, NUCLEAR reactors, NUCLEAR facility decommissioning, ACETATES, THERMAL analysis
Abstract

In this study the behavior and characteristics of two removable coatings to be deposited on a nuclear grade graphite substrate were analyzed, with the aim to evaluate their possible application on graphite bricks during dismantling operations of graphite-moderated nuclear reactors. Indeed, nowadays many shut-down reactors are still in decommissioning phase, and effective measures should be taken to guarantee safe dismantling operations. One option could be the use of coating application techniques, which mitigate the risk of graphite dusts spreading and loose contamination, protecting clean surfaces. Tested coatings, both polymeric mixtures, were selected according to their previous application history, availability in commerce and easiness in handling, whereas substrates used were non-irradiated nuclear Virgin Atcheson Graphite Ordinary Temperature (AGOT) graphite samples from L-54M Politecnico di Milano research reactor, which is in decommissioning phase. Thermal characterization of the coatings was carried out before deposition using a Thermogravimetric and Differential Thermal Analysis (TGA-DTA) equipment, tests were performed to obtain a preliminary estimation of the drying time and degradation conditions. After deposition, mechanical properties, such as hardness, of the coating were assessed. The preliminary experimental campaign showed that coating painting could be a feasible option to prevent the spread of highly contaminated graphite dusts during decommissioning of graphite components of nuclear reactors, thus ensuring clean and safe working conditions. [ABSTRACT FROM AUTHOR]

Published
2023
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38. Study of an intrinsically safe infrastructure for training and research on nuclear technologies

Author

Ripani Marco, Frambati Stefano, Mansani Luigi, Bruzzone Maurizio, Reale Marco, Monti Stefano, Ciotti Marco, Barbagallo Massimo, Colonna Nicola, Celentano Andrea, Osipenko Mikhail, Ricco Giovanni, Saracco Paolo, Viberti Carlo Maria, Frasciello Oscar, Boccaccio Pasquale, Esposito Juan, Lombardi Augusto, Maggiore Mario, Piazza Leandro A. C., Prete Gianfranco, Alba Rosa, Calabretta Luciano, Cosentino Gianluigi, Del Zoppo Antonio, Di Pietro Alessia, Figuera Pierpaolo, Finocchiaro Paolo, Maiolino Cettina, Santonocito Domenico, Schillaci Maria, Chiesa Davide, Clemenza Massimiliano, Previtali Ezio, Sisti Monica, Kostyukov Alexander, Cammi Antonio, Bortot Sara, Lorenzi Stefano, Ricotti Marco, Dulla Sandra, Ravetto Piero, Lomonaco Guglielmo, Rebora Alessandro, Alloni Daniele, di Tigliole Andrea Borio, Cagnazzo Marcella, Cremonesi Riccardo, Magrotti Giovanni, Manera Sergio, Panza Fabio, Prata Michele, and Salvini Andrea

Subjects
Physics, QC1-999
Abstract

Within European Partitioning & Transmutation research programs, infrastructures specifically dedicated to the study of fundamental reactor physics and engineering parameters of future fast-neutron-based reactors are very important, being some of these features not available in present zero-power prototypes. This presentation will illustrate the conceptual design of an Accelerator-Driven System with high safety standards, but ample flexibility for measurements. The design assumes as base option a 70 MeV, 0.75 mA proton cyclotron, as the one which will be installed at the INFN National Laboratory in Legnaro, Italy and a Beryllium target, with Helium gas as core coolant. Safety is guaranteed by limiting the thermal power to 200 kW, with a neutron multiplication coefficient around 0.94, loading the core with fuel containing Uranium enriched at 20% inserted in a solid-lead diffuser. The small decay heat can be passively removed by thermal radiation from the vessel. Such a system could be used to study, among others, some specific aspects of neutron diffusion in lead, beam-core coupling, target cooling and could serve as a training facility.

Published
2014
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40. I2S-LWR Concept Update

Author

Petrovic, Bojan, Rahnema, Farzad, Deo, Chaitanya, Garimella, Srinivas, Singh, Preet, Oh, KkochNim, Yi, Ce, Zhang, Dingkang, Manera, Annalisa, Lee, John, Downar, Thomas, Ward, Andrew, Ferroni, Paolo, Franceschini, Fausto, Salazar, David, Upadhyaya, Belle, Lish, Matt, Charit, Indrajit, Haghighat, Alireza, Memmott, Matthew, Boy, Guy, Ougouag Abderrafi, Parks, Geoffrey, Kotlyar, Dan, Ricotti, Marco, Čavlina, Nikola, Grgić, Davor, Pevec, Dubravko, Matijević, Mario, Irvin, Nick, and Hong Jiang

Subjects
I2S-LWR, Advanced reactors, Integral PWR, Inherent safety features, Accident tolerant fuel
Abstract

Pressurized water reactor of integral configuration (iPWR) offers inherent safety features, such as the possibility to completely eliminate large-break LOCA and control rod ejection. However, integral configuration implemented using the current PWR technology leads to a larger reactor vessel, which in turn, due to the vessel manufacturability and transportability restrictions, limits the reactor power. It is reflected in the fact that there are many proposed iPWR SMR concepts, with power levels up to approximately 300 MWe, but not many iPWR concepts with power level corresponding to that of large traditional PWR NPPs (900 MWe or higher). While SMRs offer certain advantages, they also have specific challenges. Moreover, large energy markets tend to prefer NPPs with larger power. The Integral Inherently Safe Light Water Reactor (I2S- LWR) concept is an integral PWR, of larger power level (1000 MWe), that at the same time features integral configurations, and inherent safety features typically found only in iPWR SMRs. This is achieved by employing novel, more compact, technologies that simultaneously enable integral configuration, large power, and acceptable size reactor vessel. This concept is being developed since 2013 through a DOE-supported Integrated Research Project (IRP) in Nuclear Engineering University Programs (NEUP). The project led by Georgia Tech includes thirteen other national and international organizations from academia (University of Michigan, University of Tennessee, University of Idaho, Virginia Tech, Florida Institute of Technology, Brigham Young University, Morehouse College, University of Cambridge, Politechnico di Milano, and University of Zagreb), industry (Westinghouse Electric Company and Southern Nuclear), and Idaho National Laboratory. This concept introduces and integrates several novel technologies, including high power density core, silicide fuel, fuel/cladding system with enhanced accident tolerance, and primary micro- channel heat exchangers integrated with flashing drums into innovative power conversion system. Many inherent safety features are implemented as well, based on all passive safety systems, enhancing its safety performance parameters. The concept aims to provide both the enhanced safety and economics and offers the next evolutionary step beyond the Generation III + systems. This paper presents some details on the concept design and its safety systems and features, together with an update of the project progress.

Published
2017

43. Design Safety Considerations for Water Cooled Small Modular Reactors Incorporating Lessons Learned from the Fukushima Daiichi Accident

Author

Alamgir, M. d., Aritomi, M., Banoori, S. M., Atique, M., Bylov, I., Choi, S., Garcia, M., Gimenez, M., Grinberg, M., Hidayatullah, H., Ingersoll, D. T., Jilani, G., Kanagawa, T., Kim, M., Koshy, T., Kuznetsov, V., Marquino, W., Nayak, A. K., Park, K. B., Qureshi, K. R., Ricotti, MARCO ENRICO, Song, D., Subki, M. H., Susyadi, S., Syarip, S., Temple, R., Ui, A., Veshnyakov, K., Yamada, K., and Zeliang, C.

Subjects
SMR, Safety, Fukushima, SMR, Safety, Fukushima
Published
2016

49. The Pioneering Role of IRIS in Resurgence of Small Modular Reactors

Author

Petrović, Bojan, Ricotti, Marco, Monti, Stefano, Čavlina, Nikola, and Ninokata, Hisashi

Subjects
IRIS, small modular reactors, Safety-by-Design™
Abstract

This paper presents an overview of the first 10 years of the IRIS project, summarizing its main technical achievements and evaluating its impact on the resurgence of Small Modular Reactors (SMRs). SMRs have been recurrently studied in the past, from early days of nuclear power, but have never gained sufficient traction to reach commercialization. This situation persisted also in the 1990s ; the focus was on large reactors based on the presumed common wisdom of this being the only way to make the Nuclear Power Plants competitive. IRIS is one of several small reactor concepts that originated in late 1990’s. However, the specific role and significance of IRIS is that it systematically pursued resolving technology gaps, addressing safety, licensing and deployment issues and performing credible economics analyses, which ultimately made it possible – together with other SMR projects – to cross the “skepticism threshold” and led the making of a convincing case – domestically and internationally – for the role and viability of smaller reactors. Technologically, IRIS is associated with a number of novel design features that it either introduced for the first time, or pursued more systematically than its predecessors and ultimately brought them to a new technical level. Some of these are discussed in this paper, such as the IRIS Safety-by-Design™, security-by-design, the innovative thermodynamic coupling of its vessel and containment, systematic PRA guided design, approach to seismic design, approach to reduce the emergency planning zone to the site boundary, active involvement of academia, and so on. Many individuals and organizations contributed to that work, too many to list individually, and this paper attempts to pay tribute at least to their collective work.

Published
2012

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