Results 51 to 60 of about 110,724 (75)

Review and Modeling of Integrated Energy Systems with Nuclear Reactor Coupled Desalination and District Heating

Nuclear science and engineering
Detailed reviews of a past advanced nuclear reactor–based integrated energy system, as well as other nuclear reactor and fossil fuel–based integrated energy systems, have been performed for this work.
Md Akhlak, Bin Aziz, C. Callaway, Nicholas R. Brown, Caleb S. Brooks   +4 more
semanticscholar   +1 more source

The Digital Nuclear Reactor Initiative: First steps towards advanced applications

EPJ Web of Conferences
A large-scale research and development project, the Digital Nuclear Reactor initiative, involving the major players in the French nuclear industry has started in 2020.
Sandrine Cochet, Arnaud Caillaux, Sophie Viot Coster, Robin Delvaux, Roland Lenain, Yohann Pipeau, Yvan Fournier, Chaï Koren, Clément Lafaurie, B. Calgaro, Cyril Patricot, Paolo Olita, C. Vaglio-Gaudard, Brayan Hourez, Anthime Farda, Dorothee Senechal, Clément Stutz, Barbara Vezzoni   +17 more
semanticscholar   +1 more source

Reduced-order modeling of neutron transport separated in axial and radial space by Proper Generalized Decomposition with applications to nuclear reactor physics

Annals of Nuclear Energy
In this article, we demonstrate the novel use of Proper Generalized Decomposition (PGD) to separate the axial and, optionally, polar dimensions of neutron transport.
K. Dominesey, Wei Ji
semanticscholar   +1 more source

Validation and Verification of ASYST Code for Predicting Condensation Phenomena in Nuclear Reactor Safety Systems

Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance
The ASYST (Adaptive System Thermal-Hydraulic) code series is a recent development that integrates the functionalities of SCDAPSIM and SAMPSON. It can simulate and analyze fluid and reactor systems with Best Estimate Plus Uncertainty (BEPU) capability ...
S. Saraswat, Mubashir Hassan, Sameer Osman, Chris Allison, Y. Addad   +4 more
semanticscholar   +1 more source

Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor

Journal of Nuclear Science and Technology
Molten salts are prospective candidates for core cooling of advanced high-temperature reactors. In the present work, a numerical investigation is performed to analyze the thermal-hydraulic performance of molten nitrate salt in a transversely grooved tube
Muhammad Awais, Waseem Siddique, Aneeq Raheem, K. Qureshi, Rab Nawaz, Syed Wajeeh Ul Hassan, Muhammad Zaki   +6 more
semanticscholar   +1 more source

Parameter identification and state estimation for nuclear reactor operation digital twin

Annals of Nuclear Energy, 2023
Helin Gong, Tao Zhu, Zhang Chen, Yaping Wan, Qing Li   +4 more
semanticscholar   +1 more source

The technology of shielding design for nuclear reactor: A review

Progress in nuclear energy (New series), 2023
Y.Q. Chen, B. Yan
semanticscholar   +1 more source

Developed borated austenitic stainless steel alloys as nuclear reactor control rods

Nuclear Engineering and Design, 2023
A. Saeed
semanticscholar   +1 more source

Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor

Annals of Nuclear Energy, 2023
Hongjian Guo, Wei Li, Jing Zhang, Yingwei Wu, Mingjun Wang, S. Qiu, G. Su, W. Tian   +7 more
semanticscholar   +1 more source

Dynamic model uncertainty analysis and control system multi-objective optimization of space nuclear reactor

Nuclear Science and Techniques
Run Luo, Jun-Liang Wu, Xiao-Lie Wang, Qi Wang, Yu Zhou, Hong-Tao Wan, Jia-Hui Zhou, Yan-Rong Wang   +7 more
semanticscholar   +1 more source