Statistical Analysis of Loss of Offsite Power Events by Andrija Volkanovski, Antonio Ballesteros Avila, Miguel Peinador Veira

“…The LOOP frequencies obtained for the French and German nuclear power plants (NPPs) during critical operation are of the same order of magnitude with the plant related events as a dominant contributor. …”
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A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem by Hanxing Liu, Han Zhang

“…The neutronics and thermal-hydraulics (N/TH) coupling behavior analysis is a key issue for nuclear power plant design and safety analysis. Due to the high-dimensional partial differential equations (PDEs) derived from the N/TH system, it is usually time consuming to solve such a large-scale nonlinear equation by the traditional numerical solution method of PDEs. …”
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The Effect of Welding Residual Stress for Making Artificial Stress Corrosion Crack in the STS 304 Pipe by Jae-Seong Kim, Bo-Young Lee, Woong-Gi Hwang, Sung-Sik Kang

“…The stress corrosion crack is one of the fracture phenomena for the major structure components in nuclear power plant. During the operation of a power plant, stress corrosion cracks are initiated and grown especially in dissimilar weldment of primary loop components. …”
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Finite Element Modeling and Analysis of Nonlinear Impact and Frictional Motion Responses Including Fluid—Structure Coupling Effects by Yong Zhao

“…A nonlinear three dimensional (3D) single rack model and a nonlinear 3D whole pool multi-rack model are developed for the spent fuel storage racks of a nuclear power plant (NPP) to determine impacts and frictional motion responses when subjected to 3D excitations from the supporting building floor. …”
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Thin-Layer Drying Model, Drying Rate, and Effective Water Diffusion Coefficient of Pelleted Feed by Wei Wang, Jiyuan Chen, Nan Jin, Hongying Wang, Liangju Wang, Junhua Wu

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Overview on Radiation Damage Effects and Protection Techniques in Microelectronic Devices by Yanru Ren, Min Zhu, Dongyu Xu, Minghui Liu, Xuehui Dai, Shengao Wang, Longxian Li

“…With the rapid advancement of information technology, microelectronic devices have found widespread applications in critical sectors such as nuclear power plants, aerospace equipment, and satellites. …”
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Online Fatigue-Monitoring Models with Consideration of Temperature Dependent Properties and Varying Heat Transfer Coefficients by HengLiang Zhang, Shi Liu, Danmei Xie, Yangheng Xiong, Yanzhi Yu, Yan Zhou, Rui Guo

“…Thermal stress failure caused by alternating operational loads is the one of important damage mechanisms in the nuclear power plants. To evaluate the thermal stress responses, the Green’s function approach has been generally used. …”
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An Alarm Method for a Loose Parts Monitoring System by Yanlong Cao, Yuanfeng He, Huawen Zheng, Jiangxin Yang

“…In order to reduce the false alarm rate and missed detection rate of a Loose Parts Monitoring System (LPMS) for Nuclear Power Plants, a new hybrid method combining Linear Predictive Coding (LPC) and Support Vector Machine (SVM) together to discriminate the loose part signal is proposed. …”
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Seismic Strength Evaluation of Corroded Reactor Containment Building by Md Samdani Azad, Duy-Duan Nguyen, Bidhek Thusa, Tae-Hyung Lee

“…Abstract The purpose of this study is to investigate the effects of the corrosion phenomenon on the seismic strength of a reactor containment building (RCB) in nuclear power plants (NPPs). A corrosion degradation model is proposed based on the rationale of NPP structures and applied to the reinforcements near the base mat of RCB. …”
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The Results of Search for the Neutrino Magnetic Moment in GEMMA Experiment by A. G. Beda, V. B. Brudanin, V. G. Egorov, D. V. Medvedev, V. S. Pogosov, M. V. Shirchenko, A. S. Starostin

“…The result of the neutrino magnetic moment measurement at the Kalinin Nuclear Power Plant (KNPP) with GEMMA spectrometer is presented. …”
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Performances of halide scintillators for the dosimetry based on gamma-ray spectrometry for environmental monitoring systems by Wanook Ji, Eunjoong Lee, Young-Yong Ji

“…Based on these results, LaBr3(Ce) and NaI(Tl) were selected as in situ gamma spectrometry system for measuring environmental radiation, and field experiments were conducted near the Fukushima Daiichi nuclear power plant to measure the dose rate.…”
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ASSESSMENT OF ENVIRONMENTAL IMPACT OF ENERGY FACILITIES IN THE ISLAMIC REPUBLIC OF IRAN BY METHOD OF BUILDING COMPOSITE THREE-DIMENSIONAL MODELS by M. A. Mehdizadeh

“…The paper demonstrates the method of building composite 3D-models applied for assessment of presumable incidents with radioactivity discharge at the nuclear power plant in Halileh, 20 km from the city of Bushehr. …”
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Miniaturized-specimen creep testing: an alternative for evaluating the remaining life of Cr-Mo steel components by Heloisa Cunha Furtado, Fernanda Figueiredo Martins dos Santos, Leonardo Sales Araújo, Levi de Oliveira Bueno

“… Creep is the main degradation mechanism in steel and superalloy components operating at high temperatures in thermal and nuclear power generation units. Therefore, acquiring creep data during equipment operation is vital for a realistic calculation of the remaining useful life of these units. …”
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RELAP5 Simulation of PKL Facility Experiments under Midloop Conditions by J. F. Villanueva, S. Carlos, F. Sanchez-Saez, I. Martón, S. Martorell

“…Nuclear power plant risk has to be quantified in full power and in other modes of operation. …”
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Developing an Empirical Relationship to Predict the Wear Characteristics of Ni-Based Hardfaced Deposits on Nuclear Grade 316LN Austenitic Stainless Steel by S. Gnanasekaran, Samson Jerold Samuel Chelladurai, G. Padmanaban, Ramesh Arthanari, V. Balasubramanian

“…Using the nickel-based Colmonoy 5 hardfacing alloy, components made of austenitic stainless steel (ASS) used in nuclear power plants can be hardfaced. Hardfacing is the process of applying complex and wear-resistant materials to substrates that require abrasion resistance. …”
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A Conceptual Approach to Eliminate Bypass Release of Fission Products by In-Containment Relief Valve under SGTR Accident by Taeseok Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Hoichul Jung, Sung Joong Kim

“…During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in nuclear power plants. However, in a bypass scenario of steam generator tube rupture (SGTR), radioactive nuclides can be released to environment even if the containment is not ruptured. …”
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Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation by Junxiao Zheng, Bin Zhang, Shengchun Shi, Yixue Chen

“…Maintaining the structural integrity of the reactor pressure vessel (RPV) is a critical concern related to the safe operation of nuclear power plants. To estimate the structural integrity over the designed lifetime and to support analyses for a potential plant life extension, an accurate calculation of the fast neutron fluence (E>1.0 MeV or E>0.1 MeV) at the RPV is significant. …”
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Mesoscale Modelling of Bond Behavior at FRP-Concrete under Mode II Loading: Effect of Rayleigh Damping by Feng-chen An, Qiong-guan Xiao, Shuai Li, Hong-jun Li

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Overview and Discussion of the OECD/NRC Benchmark Based on NUPEC PWR Subchannel and Bundle Tests by M. Avramova, A. Rubin, H. Utsuno

“…The Pennsylvania State University (PSU) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has prepared, organized, conducted, and summarized the Organisation for Economic Co-operation and Development/US Nuclear Regulatory Commission (OECD/NRC) benchmark based on the Nuclear Power Engineering Corporation (NUPEC) pressurized water reactor (PWR) subchannel and bundle tests (PSBTs). …”
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Prediction of Strength and Quality Control of Monolithic Concrete Laying in Structures with Permanent Formwork by D. N. Korotkih, D. Е. Kapustin

“…When erecting a number of nuclear power plant structures, a precast-monolithic construction technology is used using reinforced formwork blocks consisting of a reinforcing frame and permanent formwork made of steel fiber concrete. …”
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