Search Results - "Nuclear engineering and design"

A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications by Wu, Pan, Ma, Yunduo, Gao, Chuntian, Liu, Weihua, Shan, Jianqiang, Huang, Yanping, Wang, Junfeng, Zhang, Dan, Ran, Xu

“…Supercritical carbon dioxide (S-CO2) Brayton cycle has many advantages including high power conversion efficiency at mediate temperature, compact…”
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Current status of materials development of nuclear fuel cladding tubes for light water reactors by Duan, Zhengang, Yang, Huilong, Satoh, Yuhki, Murakami, Kenta, Kano, Sho, Zhao, Zishou, Shen, Jingjie, Abe, Hiroaki

“…Zirconium-based (Zr-based) alloys have been widely used as materials for the key components in light water reactors (LWRs), such as fuel claddings which suffer…”
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Preliminary design of the suppressive containment system based on HPR1000 by Qi, Xiangjie, Yu, Fangxiaozhi, Meng, Zhaoming, Sun, Zhongning, Zhang, Nan, Guo, Zehua

“…•A preliminary containment design has been developed for the HPR1000, Compared with HPR1000, the system and equipment of the conceptual design have been…”
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Heavy metal oxide glasses as gamma rays shielding material by Kaur, Preet, Singh, Devinder, Singh, Tejbir

“…The gamma rays shielding parameters for heavy metal oxide glasses and concrete samples are comparable. However, the transparent nature of glasses provides…”
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Inverse uncertainty quantification using the modular Bayesian approach based on Gaussian process, Part 1: Theory by Wu, Xu, Kozlowski, Tomasz, Meidani, Hadi, Shirvan, Koroush

“…•We developed a robust framework for inverse Uncertainty Quantification using Bayesian inference.•Inverse UQ can more precisely quantify uncertainties in…”
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Fluid flow and convective heat transfer to fluids at supercritical pressure by Jackson, J.D.

“…The feature of fluids at pressures just above the critical value which makes them of particular interest is that they change in a continuous manner from being…”
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Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor by Tian, Zhixing, Liu, Xiao, Wang, Chenglong, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H.

“…•The heat transfer behavior of high temperature heat pipe is experimentally tested.•The effects of heating power and inclination angle are studied.•Overheating…”
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Physics-informed reinforcement learning optimization of nuclear assembly design by Radaideh, Majdi I., Wolverton, Isaac, Joseph, Joshua, Tusar, James J., Otgonbaatar, Uuganbayar, Roy, Nicholas, Forget, Benoit, Shirvan, Koroush

“…Optimization of nuclear fuel assemblies if performed effectively, will lead to fuel efficiency improvement, cost reduction, and safety assurance. However,…”
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Status of research and development of learning-based approaches in nuclear science and engineering: A review by Gomez-Fernandez, Mario, Higley, Kathryn, Tokuhiro, Akira, Welter, Kent, Wong, Weng-Keen, Yang, Haori

“…Nuclear technology industries have increased their interest in using data-driven methods to improve safety, reliability, and availability of assets. To do so,…”
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The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles by Chen, S.K., Chen, Y.M., Todreas, N.E.

“…•Aspects of Cheng Todreas correlation (CTD) have been improved, producing UCTD.•Laminar to transition boundary was reassessed to be much lower values.•The…”
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Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR) by Satvat, Nader, Sarikurt, Fatih, Johnson, Kevin, Kolaja, Ian, Fratoni, Massimiliano, Haugh, Brandon, Blandford, Edward

“…•A generic FHR design benchmark data set.•Neutronic, Thermal-Hydraulic and Pebble flow analysis.•Coupling of Monte Carlo, Porous Media and Discrete Element…”
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Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor by Zhang, Zeqin, Chai, Xiaoming, Wang, Chenglong, Sun, Hao, Zhang, Dalin, Tian, Wenxi, Qiu, Suizheng, Su, G.H

“…•A numerical code is carried out based on the three-stage model of frozen startup of the heat pipe.•The heat transfer performance of a NaK heat pipe is…”
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Supercritical water heat transfer coefficient prediction analysis based on BP neural network by Ma, Dongliang, Zhou, Tao, Chen, Jie, Qi, Shi, Ali Shahzad, Muhammad, Xiao, Zejun

“…[Display omitted] •A new method predict heat transfer coefficient of supercritical water.•This new method has a relatively higher accuracy.•It can analyze the…”
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MOOSE: A parallel computational framework for coupled systems of nonlinear equations by Gaston, Derek, Newman, Chris, Hansen, Glen, Lebrun-Grandié, Damien

“…Systems of coupled, nonlinear partial differential equations (PDEs) often arise in simulation of nuclear processes. MOOSE: Multiphysics Object Oriented…”
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A review on UREX processes for nuclear spent fuel reprocessing by Kumari, Indu, Kumar, B.V.R., Khanna, Ashok

“…•Details of UREX and variants of UREX + processes for reprocessing of spent nuclear fuels.•UREX + process consists of nine versions from which seven products…”
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On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives by Fiorina, Carlo, Clifford, Ivor, Kelm, Stephan, Lorenzi, Stefano

“…In the last two decades, the use of OpenFOAM as a multi-physics library for nuclear applications has grown from a sporadic use for exploratory studies to a…”
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Dependence assessment in human reliability analysis based on D numbers and AHP by Zhou, Xinyi, Deng, Xinyang, Deng, Yong, Mahadevan, Sankaran

“…•D numbers and AHP are combined to implement dependence assessment in HRA.•A new tool, called D numbers, is used to deal with the uncertainty in HRA.•The…”
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Molten salt reactor waste and effluent management strategies: A review by Riley, Brian J., McFarlane, Joanna, DelCul, Guillermo D., Vienna, John D., Contescu, Cristian I., Forsberg, Charles W.

“…Molten salt reactors (MSRs) are being considered as one of the potential nuclear options to meet future energy demands. While the MSR designs are drastically…”
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Wire-mesh sensors: A review of methods and uncertainty in multiphase flows relative to other measurement techniques by Tompkins, Casey, Prasser, Horst-Michael, Corradini, Michael

“…•Void fraction uncertainty via measurement with wire-mesh sensors is less than 11% relative to secondary measurement methods (e.g. radiative, high speed…”
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Radiation effects in concrete for nuclear power plants – Part I: Quantification of radiation exposure and radiation effects by Field, K.G., Remec, I., Pape, Y. Le

“…•Neutron and gamma rays fields in concrete biological shield are calculated.•An extensive database on irradiated concrete properties has been…”
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