Fuzzy TSMCSPO for Trajectory Tracking of Nuclear Reactor Dismantlement Robot Manipulator gan Chengqian Li, Hamza Khan, Jinwon Lee, Jaehyung Kim, Min Cheol Lee

“...In this study, a fuzzy logic system to tune the parameters of terminal sliding mode control with a sliding perturbation observer (TSMCSPO) in real-time is proposed according to the system’s state changes to improve the control performance of TSMCSPO for a 5-DOF robot manipulator used for nuclear reactor dismantlement. Accurate trajectory tracking control is required when using a multi-DOF robot manipulator to cut the decommissioned nuclear reactor. ...”
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Numerical Solution of Fractional Neutron Point Kinetics Model in Nuclear Reactor gan Nowak Tomasz Karol, Duzinkiewicz Kazimierz, Piotrowski Robert

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Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly gan Leonardo Acosta Martínez, Carlos Rafael García Hernández, Jesus Rosales García, Annie Ortiz Puentes

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Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly gan Leonardo Acosta Martínez, Carlos Rafael García Hernández, Jesus Rosales García, Annie Ortiz Puentes

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The Superphénix Fast Breeder Nuclear Reactor: Cross-border Cooperation and Controversies gan Claire Le Renard

“...The "Superphénix" fast breeder nuclear reactor was a Franco-Italian-German project resulting from a shared ambition to develop new technology through European industry collaboration in the 1960s-1970s. ...”
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Prediction of prestressing losses for long term operation of nuclear reactor buildings gan Thillard G., Cornish-Bowden I., Capra B.

“...Prestressed concrete is used in nuclear reactor buildings to guarantee containment and structural integrity in case of an accident. ...”
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Research Status and Suggestions of Nuclear Reactor Online Core Monitoring System gan LI Jinggang, LI Wenhuai, ZHANG Xiangju, WANG Junling, WANG Ting, LU Haoliang, PENG Sitao

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A proposal of cooling source on full power loss in nuclear reactors gan Yoshihiko HARAMURA, Nobuyuki KUBOKI

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A Nuclear Reactor Transient Methodology Based on Discrete Ordinates Method gan Shun Zhang, Bin Zhang, Penghe Zhang, Hui Yu, Yixue Chen

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Optimizing the Design of Small Fast Spectrum Battery-Type Nuclear Reactors gan Staffan Qvist

“...This study is focused on defining and optimizing the design parameters of inherently safe “battery” type sodium-cooled metallic-fueled nuclear reactor cores that operate on a single stationary fuel loading at full power for 30 years. ...”
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Measurements of stable ruthenium fission products in nuclear reactor fuel samples gan Genna M. Patton, Zachary A. Torrano, Amanda Salazar, Jeffrey Miller, Matthew E. Sanborn, Susan K. Hanson

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Energy Analysis for the Connection of the Nuclear Reactor DEMO to the European Electrical Grid gan Sergio Ciattaglia, Maria Carmen Falvo, Alessandro Lampasi, Matteo Proietti Cosimi

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Core neutron source generation method for nuclear reactor shielding calculation gan ZHANG Pingxun, ZHANG Bin, CHEN Yixue

“...The apparent differences between core sources are related to their geometric model, burnup, and power distribution.PurposeThis study aims to improve the calculation accuracy of the core neutron source for nuclear reactor shielding.MethodsFirstly, the geometric weight of each component in the core was generated by analyzing the characteristics of the radial source distribution on the basis of neutron importance, and the fine source mesh calculation was conducted for the peripheral components with high geometric weight and the region with a large power gradient. ...”
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Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly gan Leonardo Acosta Martínez, Carlos Rafael García Hernández, Jesus Rosales García, Annie Ortiz Puentes

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Chemical perspective on radionuclide emissions as atmospheric contaminants from nuclear reactors gan Sergey Travin, Gheorghe Duca, Oleg Gromov

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Development of boron carbide concrete for enhanced radiation shielding in nuclear reactors gan P. Gokul, J. Ashok Kumar, R. Preetha, Sudipta Chattopadhyaya, Pew Basu, M. Menaka, V. Subramanian, B. Venkatraman, Dhanya Sathyan, K. Jayanarayanan, Mini K. Madhavan

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Review of JAEA’s Monte Carlo codes for nuclear reactor core analysis gan Nagaya Yasunobu

“...Japan Atomic Energy Agency (JAEA) has been developing a general-purpose continuous-energy Monte Carlo code MVP for nuclear reactor core analysis. Recently improvements to MVP have been focused on the development of an advanced neutronics/thermal-hydraulics coupling code. ...”
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Global risk of radioactive fallout after major nuclear reactor accidents gan J. Lelieveld, D. Kunkel, M. G. Lawrence

“...The recent decision by Germany to phase out its nuclear reactors will reduce the national risk, though a large risk will still remain from the reactors in neighbouring countries....”
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Linear stability analysis of a nuclear reactor using the lumped model gan Kale Vivek A., Kumar Rakesh, Obaidurrahman K., Gaikwad Avinash J.

“...The stability analysis of a nuclear reactor is an important aspect in the design and operation of the reactor. ...”
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Classification of Nuclear Reactor Operations Using Spatial Importance and Multisensor Networks gan Jake Tibbetts, Bethany L. Goldblum, Christopher Stewart, Arman Hashemizadeh

“...Distributed multisensor networks record multiple data streams that can be used as inputs to machine learning models designed to classify operations relevant to proliferation at nuclear reactors. The goal of this work is to demonstrate methods to assess the importance of each node (a single multisensor) and region (a group of proximate multisensors) to machine learning model performance in a reactor monitoring scenario. ...”
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