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Transactions of the American Nuclear Society - Volume 122最新文献

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Pressurizer Model and PLCs for Investigation of Cybersecurity of PWR Plants 压水堆稳压器网络安全研究模型与plc
Pub Date : 2020-06-01 DOI: 10.13182/t32372
Ragai Altamimi, M. El-Genk, T. Schriener
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引用次数: 0
Potential Improvements in Human Error Probability Seed Optimizer Algorithms 人为错误概率种子优化算法的潜在改进
Pub Date : 2020-06-01 DOI: 10.13182/t32609
N. DeKett
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引用次数: 0
Assessment of the Thermal-Structural Characteristics of Core Components in a Preconceptual Design of the Transformational Challenge Reactor 转换挑战堆概念前设计中核心部件热结构特性评估
Pub Date : 2020-06-01 DOI: 10.13182/t32634
B. Betzler, C. Jesse, J. Sterbentz
The Transformational Challenge Reactor (TCR) is a megawatt-scale microreactor currently being designed at Oak Ridge National Laboratory (ORNL). The TCR will demonstrate the feasibility of designing, building, and operating a micro-reactor using advanced manufacturing technologies with conventionally manufactured fuel. This paper focuses on evaluating the thermal and structural characteristics of the components within a preconceptual core design of the TCR. To accomplish this a conjugate heat transfer model was developed with the computational fluid dynamics (CFD) code, Star-CCM+ [1] and a thermalmechanical model was developed with the finite element analysis (FEA) code, Abaqus [2].
转换挑战反应堆(TCR)是目前正在橡树岭国家实验室(ORNL)设计的兆瓦级微反应堆。TCR将展示使用先进制造技术和传统制造燃料设计、建造和运行微型反应堆的可行性。本文着重于评估TCR概念前核心设计中组件的热学和结构特性。为此,利用计算流体力学(CFD)程序Star-CCM+[1]建立了一个共轭传热模型,并用有限元分析(FEA)程序Abaqus[2]建立了一个热力学模型。
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引用次数: 0
Betavoltaic Nuclear Microbattery Based on Graphene/Si Schottky Junction 基于石墨烯/硅肖特基结的倍他伏打核微电池
Pub Date : 2020-06-01 DOI: 10.13182/t32066
Y. Han, C. Li, T. Li, W. Liu, X. Wang, J. Zhang
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引用次数: 0
MPCORE Code for OPR-1000 Transient Multiphysics Simulation with Adaptive Step Size Control 具有自适应步长控制的OPR-1000瞬态多物理场仿真MPCORE代码
Pub Date : 2020-06-01 DOI: 10.13182/t32441
A. Cherezov, H. Kim, Deokjung Lee, J. Park
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引用次数: 2
Power Level Downselection for the Transformational Challenge Reactor 转换挑战反应堆的功率水平下降选择
Pub Date : 2020-06-01 DOI: 10.13182/t32129
B. Ade, B. Betzler, N. Brown, M. Greenwood, J. Heineman, P. Jain, R. Kile, J. Rader, K. Terrani, A. Wysocki
government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doepublic-access-plan). Power Level Downselection for the Transformational Challenge Reactor
通过接受文章的出版,出版商承认美国政府保留非排他性的、付费的、不可撤销的、全球范围的许可,以出版或复制该手稿的出版形式,或允许其他人为美国政府的目的这样做。美国能源部将根据美国能源部公共访问计划(http://energy.gov/downloads/doepublic-access-plan)向公众提供这些由联邦政府资助的研究成果。转换挑战反应堆的功率水平下降选择
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引用次数: 3
Adjoint Driven Ex-Core Response Estimation in PWR with Thermal Feedback 带热反馈的压水堆伴随驱动堆前响应估计
Pub Date : 2020-06-01 DOI: 10.13182/t32431
S. Henderson, T. Pandya, S. Stimpson
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引用次数: 0
Impact of Fission Product Content on Phase Development in U3Si2 Fuel 裂变产物含量对U3Si2燃料相发展的影响
Pub Date : 2020-06-01 DOI: 10.13182/t32018
D. Adorno, T. Besmann, A. Claisse, K. Johnson, V. Kocevski, J. Mcmurray, T. Ulrich, J. White
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引用次数: 0
Development of an NPP VDCS Verification Platform 核电厂VDCS验证平台的开发
Pub Date : 2020-06-01 DOI: 10.13182/t32071
Q. Ma, J. Qing, H. Sun, P. Sun, X. Wei
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引用次数: 0
Automated Functional Testing for Nuclear Digital Instrumentation and Control Systems 核数字仪表和控制系统的自动化功能测试
Pub Date : 2020-06-01 DOI: 10.13182/t32428
C. Maddux, D. Mccarter, G. Morton, B. Shumaker
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引用次数: 0
期刊
Transactions of the American Nuclear Society - Volume 122
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