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10th Asian Physics Symposium 2023, APS 2023

作者： Amatullah, Amila Permana, Sidik Pramuditya, Syeilendra Master Program in Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia Graduate Program in Nuclear Science and Engineering Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia Graduate Program in Physics Faculty of Mathematics and Natural Sciences Bandung Institute of Technology Ganesha No. 10 Bandung Indonesia

One strategy for emission reduction in Indonesia is the dedieselization program, replacing diesel power plants with renewables. Pressurized Water Reactor (PWR) type Small Modular Reactor (SMR) is also a consideration. This study aims to compare fuel performance in SMRs. Four fuel types with varying fissile and fertile nuclides but equal fissile mass percentages were assessed: U235- U238, U235-Th232, U233-U238, and U233-Th232, using PIJ SRAC 2006 and JENDL 4.0. Parameters include neutron multiplication factor, conversion ratio, and isotope production. Results indicated that U233-U238 has a highest initial neutron multiplication factor, 1.55. Substituting uranium-238 with thorium-232 boosts neutron flux and conversion, reducing nuclear proliferation risk. While initial neutron multiplication may not be highest, thorium-232 can produce uranium-233 with high initial neutron multiplication factor. This research aids fuel selection for Indonesia SMR dedieselization program. © Published under licence by IOP Publishing Ltd.

关键词： Thorium

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On the viability of wearing evaluation by Thin Layer Activation in the presence of non-occupationally exposed individuals

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nuclear Science and Techniques 2022年第3期33卷 103-112页

作者： Michel de Almeida Franca Julio Cezar Suita Paulo Fernando Ferreira Frutuoso e Melo Celso Marcelo Franklin Lapa Graduate Program of Nuclear Engineering COPPEFederal University of Rio de JaneiroRio de JaneiroRJ 21941914Brazil Instituto de Engenharia Nuclear(IEN-CNEN) Rio de Janeiro 21941614Brazil Comissao Nacional de Energia Nuclear(SEASE/DRS/CNEN) Rio de Janeiro 22290040Brazil

Thin Layer Activation is a nuclear technique that has key advantages over other wear measuring techniques for mechanical systems,especially for in site experiments on equipment important to safety in nuclear ***,it incurs radioactive dose and,thus,must be proved radiologically safe before use,otherwise,the utilization of this technique may be hindered *** said technique is safe previous to any operational/monetary cost is key,providing a methodology for this early assertion is the main contribution of this work—here,only non-occupationally exposed individuals are *** work offers a methodology,through a case study,to ascertain the Thin Layer Activation parameters to obtain safe levels of radioactive dose while maintaining statistically reliable *** methodology consists of using simulations,through the Monte Carlo Method,to obtain the floors and ceilings for the previously mentioned activation parameters based on operation and work conditions on site.

关键词： Thin Layer Activation Safety evaluation Simulation Equipment wearing

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COGNITIVE MODELS FOR HUMAN RELIABILITY ANALYSIS APPLICATIONS TO THE OIL & GAS INDUSTRY 42

COGNITIVE MODELS FOR HUMAN RELIABILITY ANALYSIS APPLICATIONS...

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ASME 2023 42nd International Conference on Ocean, Offshore and Arctic engineering, OMAE 2023

作者： Alvarenga, M.A.B. Melo, P. F. Frutuoso E Maturana, M.C. Martins, M.R. National Commission of Nuclear Energy RJ Rio de Janeiro Brazil Graduate Program of Nuclear Engineering Federal University of Rio de Janeiro RJ Brazil University of São Paulo Brazil

ISBN: (纸本)9780791886847

In the quantitative risk analysis (QRA) of O & G equipment, it is necessary to consider the application of cognitive models (in use in the nuclear industry), which can very effectively predict human performance. First generation Human Reliability Analysis (HRA) methods are used in O&G primarily in an emergency scenario QRA and second-generation methods for design and normal operation. These methods can be inefficient. First generation HRA models do not have a cognitive architecture capable of processing human information. Secondgeneration models consider mechanisms of cognitive errors. Most of third generation HRA models are dynamic simulations of cognitive tasks, coupled with an event/accident simulation code, often designed more for human-machine interface assessment than for human error analysis. There are also cognitive psychology models designed to assess human performance without the intention of serving as HRA tools. These models have a detailed understanding of the cognitive mechanisms of human error, which is the key to a complete HRA model. One of these models, ACT-R, contains adequate quantification to serve as an HRA model. This article discusses cognitive psychology models and their internal structures in human information processing to provide human error probabilities that arise from the architecture itself and are not dependent on Performance Shaping Factors (PSFs), which are quantified by HRA current methodologies. Copyright © 2023 by ASME.

关键词： nuclear industry

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INFLUENCE OF TORREFACTION SEVERITY ON WOOD BLEND FROM AMAZONIAN RESIDUES 31st

INFLUENCE OF TORREFACTION SEVERITY ON WOOD BLEND FROM AMAZON...

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31st European Biomass Conference and Exhibition, EUBCE 2023

作者： Souto, Normando P. B. Chaves, Bruno S. Macedo, Lucélia A. Lamas, Giulia Cruz Barbosa, Thais de Rodrigues, Pedro Paulo O. Cardoso, Marcela Rodrigues Rousset, Patrick Silveira, Edgar A. Military Institute of Engineering Nuclear Engineering Graduate Program Rio de Janeiro Brazil Brasilia DF 70818-900 Brazil University of Brasília Mechanical Sciences Graduate Program Laboratory of Energy and Environment Brasilia-DF 70910-900 Brazil 73 Rue J. F. Breton Cedex 5 Montpellier34398 France

This study investigated and characterized the torrefaction treatment of Amazonian wood residues blend. Six wood residue materials from legal wood processing from the Jacundá National Forest (Rondônia, Brazil) were blended and torrefied at 225, 250 and 275 °C for 60min in an inert atmosphere (N2). The wood residues comprised Peltogyne lecointei (S1), Erisma uncinatum (S2), Martiodendron elatum (S3), Handroanthus incanus (S4), Dipteryx odorata (S5), and Allantoma decandra (S6). The solid yield (SY) and torrefaction severity index (TSI) were applied to evaluate the torrefaction process severity. The pyrolysis of torrefied biomass and chemical analysis (proximate, ultimate, and calorific) allowed to evaluate the influence of torrefaction severity on the blend. The preliminary results showed that torrefaction temperature highly affects the blended samples, with a weight loss of 4.9% for 225 °C and 34.96% for 275 °C torrefaction. A goodness of fit was achieved between the calculated TSI and volatile matter (R2 =0.99), fixed carbon (R2 =0.99), and ash contents (R2 =0.93). HHV showed an improvement of up to 7% for 275 °C torrefaction. The results provided valuable information to determine the process parameters for further torrefaction and pelletizing processes (TAP) aiming at fuel production in decentralized systems, reducing diesel dependence on the Amazon region. © 2023 ETA-Florence Renewable Energies.

关键词： Blending

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A Monte Carlo Uncertainty Propagation on the Accident Rate of a Plant Equipped with a Single Protection Channel Considering Truncated Probability Distributions 32nd

A Monte Carlo Uncertainty Propagation on the Accident Rate o...

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32nd European Safety and Reliability Conference, ESREL 2022

作者： Araújo, E.P.M. Martins, M.C. Teixeira, D.G. e Melo, P. F. Frutuoso Department of Nuclear Engineering Polytechnic School Federal University of Rio de Janeiro Rio de Janeiro Brazil Graduate Program of Nuclear Engineering COPPE Federal University of Rio de Janeiro Rio de Janeiro Brazil

ISBN: (纸本)9789811851834

We consider a plant equipped with a single protection channel whose demand, failure, and repair times follow exponential distributions. However, we may not know the parameters of these distributions precisely;this is due to variability on them and parameter ranges may be found. This lack of plant specific data gives rise to plant-to-plant data variability. In this sense, the available information may be translated as a probability distribution and it is necessary to perform an uncertainty propagation on the plant accident rate to assess the impact of the variability of the parameters used. We use a lognormal distribution for this purpose because all rates may be written as m × 10n, where 0 © 2022 ESREL2022 Organizers. Published by Research Publishing, Singapore.

关键词： Normal distribution

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A FRAMEWORK FOR DEFINING RISK-BASED INSPECTION PLANS FOR SUBSEA EQUIPMENT 42

A FRAMEWORK FOR DEFINING RISK-BASED INSPECTION PLANS FOR SUB...

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ASME 2023 42nd International Conference on Ocean, Offshore and Arctic engineering, OMAE 2023

作者： Schleder, Adriana M. Maturana, Marcos C. Martins, Marcelo R. Melo, Paulo F. F. Frutuoso E. de Barros, Leonardo O. Orlowski, Rene T. C. Naval Architecture and Ocean Engineering Department University of São Paulo São Paulo Brazil COPPE Graduate Program of Nuclear Engineering Federal University of Rio de Janeiro Rio de Janeiro Brazil Research and Development Center CENPES Petrobras Rio de Janeiro Brazil

ISBN: (纸本)9780791886847

Cost and risk optimization is a central issue in the offshore Oil and Gas sector, and risk-based approaches has been more and more employed to assist the segment in the concretization of that goal. In this sense, the use of Risk Based Inspection by the oil industry has increased. The inspection procedure aims mitigating the uncertainty related to the asset degradation state, enabling a better quantification of the actual damage, and, consequently, increasing the accuracy of remaining life projections. However, the costs involved in offshore subsea inspections are considerable. Therefore, the optimization of inspection plans plays a crucial role in the definition of an asset management program economically balanced. To perform an efficient optimization, it is important not only obtain an effective optimization algorithm but also achieve a high quality of the information used as input. In other words, an adequate definition of the risk indexes used is necessary, as well as the entire process used to quantify them. In this context, this paper presents a framework for obtaining the optimized inspection plans, starting from the assessment of the risk associated with the failure modes, moving on through the process of defining risk indices and, finally, presenting the optimization process itself. In this way, the framework proposed presents all the phases necessary to obtain optimized inspection plans, including the stage of preparation for the optimization process. Finally, the application of the proposed framework is illustrated by the elaboration of the inspection plans for a subsea manifold. Copyright © 2023 by ASME.

关键词： Inspection

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Novel photocatalytic coating for corrosion mitigation in 304LSS of dry storage canisters

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Frontiers in Materials 2023年 10卷

作者： Sathasivam, Kamalasekaran Wang, Mei-Ya Anbalagan, Aswin kumar Lee, Chih-Hao Yeh, Tsung-Kuang Nanoscience and Technology Program Taiwan International Graduate Program Academia Sinica Taipei Taiwan Department of Engineering and System Science National Tsing Hua University Hsinchu Taiwan Nuclear Science and Technology Development Center National Tsing Hua University Hsinchu Taiwan Institute of Nuclear Engineering and Science National Tsing Hua University Hsinchu Taiwan

Type 304L stainless steel (304LSS) is one of the candidate canister materials for storing radioactive spent fuels, usually near seashore environments along with nuclear power plants. During the prolonged exposure of dry storage canisters to saline environments, they are highly susceptible to chloride induced stress corrosion cracking. Failure of a dry storage canister not only would release radioactive isotopes into the environment, but would also lead to a costly replacement of the cracked canister. The objective of this study is to develop a multilayered titanium dioxide (TiO2) composite coating on a 304LSS substrate. With ultraviolet (UV) illumination, this coating would act as a barrier and simultaneously offer cathodic protection against corrosion in the substrate alloy. The composite coating consists of a plain amorphous TiO2 coating over another cerium-doped (Ce-doped) TiO2 coating. Electronic currents generated by photo-catalytic reaction of the amorphous TiO2 coating under UV illumination were measured. Photo-electrochemical analyses and surface morphology observations were conducted to evaluate the performance of the Ce-doped coatings on corrosion mitigation. Optimal amounts of cerium doping that offered better photo-cathodic protection were also explored. Results indicated that the Ce-doped TiO2 coating exhibited a better performance on photo-cathodic protection for 304L stainless steel in aerated 3.5% NaCl solutions than the one without cerium doping. The underlying Ce-doped TiO2 coating was effectively charged during UV illumination, and it was able to continuously release electrons even after the UV was switched off, thus providing uninterrupted photo-cathodic protection for the coated 304L stainless steel substrate. Copyright © 2023 Sathasivam, Wang, Anbalagan, Lee and Yeh.

关键词： Titanium dioxide

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Component Criticality Rating of a Subsea Manifold using FMECA 32nd

Component Criticality Rating of a Subsea Manifold using FMEC...

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32nd European Safety and Reliability Conference, ESREL 2022

作者： Nicolau, Andressa S. Martins, Maximiano C. Paulo, Fernando F. Melo, Frutuoso E. Schleder, Adriana M. Martins, Marcelo R. De Barros, Leonardo O. Orlowski, Rene Thiago C. COPPE Graduate Program of Nuclear Engineering Federal University of Rio de Janeiro Rio de Janeiro Brazil LabRisco Analysis Evaluation and Risk Management Laboratory Naval Architecture and Ocean Engineering Department University of Sao Paulo Sao Paulo Brazil CENPES Research and Development Center of Petrobras Petrobras Brazil

ISBN: (纸本)9789811851834

Subsea manifold is a metallic structure fixed to the seabed, in which valves and accessory equipment are installed that make it possible to couple Wet Christmas Trees and other production systems (such as Pipeline End Manifold, Pipeline End Termination and risers);it is required during the completion and production of oil and gas wells. The failure of the subsea manifold can cause serious damage to the environment and human health, as well as stop production causing the loss of large foreign exchange, so ensuring its integrity is extremely important for the sector. In this article a Failure Mode, Effects and Criticality Analysis is presented for the criticality classification of the components of a typical subsea manifold cluster, Pipeline end manifold and Pipeline end termination. The final effect of equipment failure in the manifold was evaluated as a function of production interruption, production reduction, rupture, environmental pollution, plugging, leakage and structural collapse. Different means of detection were considered. The results of this study provide information about the weakness of the subsea manifold equipment. It is expected that this paper can contribute to future analysis of similar equipment and means to contribute to future work involving risk analysis, and inspection maintenance plan. © 2022 ESREL2022 Organizers. Published by Research Publishing, Singapore.

关键词： Christmas trees (wellheads)

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Evaluation of the Probability of Overflow from the Abadia De Goiás Repository by the Fokker-Planck Equation Using the Trotter's Formula

SSRN

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SSRN 2023年

作者： Gabcan, Ludmila Alves, Antonio Sergio M. da Silva, Fernando Carvalho Teixeira, Danielle G. Frutuoso e Melo, Paulo Fernando COPPE Graduate Program of Nuclear Engineering Federal University of Rio de Janeiro RJ Rio de Janeiro Brazil Eletronuclear S.A. RJ Rio de Janeiro Brazil

A model was constructed with the objective of developing the Fokker-Planck equation for the calculation of the reliability attributes required for risk-informed decision-making involved in the analysis of water infiltration inside the repository located in the Abadia de Goiás municipality, in the metropolitan region of the city of Goiânia. The solution of the Fokker-Planck equation was analytically obtained by the Trotter’s method for a near surface repository. This solution provides the probability density and the probability functions for the height of the liquid (water + radionuclides) column, generated by the infiltrated water in the concrete crypt of the repository. The modeling was unidimensional, and the calculations were performed for the geometric center of the repository crypt, which is the place of greater sensitivity of occurrence of accidental scenarios. The concept of the present model can be extended to other places in the crypt without loss of generality. The developed model is appropriate to analyze the repository overflow, a kind of event that occurs when the height of the liquid column inside the repository reaches the value of the inner height of the concrete crypt of the facility. This accident scenario produces the greatest release of radioactive material to the region outside the repository and, consequently, it is responsible for the main radiological impact for both members of the public and the environment. Calculations performed for the Abadia de Goiás repository indicated that the overflow probability for this facility is strongly dependent on the rainfall rate and also on the institutional time period, varying from about 3% with no rainfall penetration up 99% with the maximum rainfall rate for an institutional time period control of 300 yr. Such results can help making decisions on the problem of risk scenarios related to the disposal of radioactive waste. © 2023, The Authors. All rights reserved.

关键词： Risk perception

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Reactivity sensitivity analysis for a fuel rod with biconcave cross section in a PWR 29

Reactivity sensitivity analysis for a fuel rod with biconcav...

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29th European Safety and Reliability Conference, ESREL 2019

作者： Oliveira, M.V.A. Teixeira, D.G. Roberto, T.D. Henrice, E. Frutuoso e Melo, P.F. Graduate Program of Nuclear Engineering Federal University of Rio de Janeiro/COPPE Brazil

ISBN: (纸本)9789811127243

The objective of this work is to make a preliminary reactivity analysis of an original design of a fuel rod with biconcave cross section. In this phase of the project, reactivity sensitivity tests were carried out through the subchannel area, considering UO2 fuel enriched at 4% and 5%, for the fuel temperatures of 600K and 900K. We observed that the best area ranges were the regions from 7.5 to 7.9 cm2 for the UO2 enrichment of 5% and from 6.2 to 6.6 cm2 for the UO2 enrichment of 4%. The next step will be a study of the fuel temperature coefficient. © 2019 European Safety and Reliability Association. Published by Research Publishing, Singapore.

关键词： Uranium dioxide

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