Volume 9 Issue 4 | ASME J. of Nuclear Rad Sci.

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Special Papers

Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

Keke Hou, Chao Yan, Peng Wang, Changqing Cao, Jun Lin, Yanguang Cui, Junqiang Lu, Libing Zhu

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041101. doi: https://doi.org/10.1115/1.4062795

Abstract

View articletitled, Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

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Topics: Alloys , Fuels , Sintering , Uranium , Thermal conductivity , Density

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041102. doi: https://doi.org/10.1115/1.4056854

Abstract

View articletitled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

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Topics: Coolants , Flow (Dynamics) , Fuels , Sodium , Temperature , Accidents , Transients (Dynamics) , Pins (Engineering)

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103. doi: https://doi.org/10.1115/1.4056772

Abstract

View articletitled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

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Topics: Coolants , Design , Diluents , Fuels , Leakage , Neutrons , Supercritical carbon dioxide , Nuclear fission , Nuclides , Feedback

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104. doi: https://doi.org/10.1115/1.4062119

Abstract

View articletitled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

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Topics: Additive manufacturing , Computational fluid dynamics , Design , Fuels , Particulate matter , Temperature , Coolants , Neutrons , Heat transfer , Computer software

Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant

Li Yulong, Liu Feng, Liu Xiajie, Li Li, Kang Zheng, He Ye

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041105. doi: https://doi.org/10.1115/1.4062796

Abstract

View articletitled, Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant

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Topics: Composite materials , Gamma rays , Mechanical properties , Nuclear power stations , Pressurized water reactors , Radiation (Physics) , Silicone rubber , Particle size

Main Parameters Influencing the Level of Labile Contamination and the Removal Factor

Pierrick Agullo, Alban Gossard, Gilles Ranchoux, Emmanuel Porcheron, Fabrice Petitot

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041106. doi: https://doi.org/10.1115/1.4062550

Abstract

View articletitled, Main Parameters Influencing the Level of Labile Contamination and the Removal Factor

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Topics: Contamination , Surface roughness , Pressure , Temperature , Drying

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107. doi: https://doi.org/10.1115/1.4062879

Abstract

View articletitled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

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Topics: Molten salt reactors , Simulation , Wall thickness , Safety , Computer simulation , Design , Temperature , Heat conduction , Melting , Solidification

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108. doi: https://doi.org/10.1115/1.4056973

Abstract

View articletitled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

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Topics: Cycles , Heat exchangers , Sensitivity analysis , Water , Fast neutron reactors , Conceptual design , Temperature , Heat , Bathythermographs , Geometry

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041109. doi: https://doi.org/10.1115/1.4056974

Abstract

View articletitled, Hydrogen Loading System for Thin Films for Betavoltaics

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Topics: Hydrogen , Palladium , Temperature , Leakage , Pressure drop , Thin films

Research Papers

Next Generation/Advanced Reactors

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Nico Krauter, Alexandru Aurelian Onea, Gunter Gerbeth, Sven Eckert

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301. doi: https://doi.org/10.1115/1.4062239

Abstract

View articletitled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

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Topics: Eddies (Fluid dynamics) , Flow (Dynamics) , Flowmeters , High temperature , Sensors , Sodium , Temperature , Wire , Eddy currents (Electricity) , Liquid metals

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302. doi: https://doi.org/10.1115/1.4062500

Abstract

View articletitled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

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Topics: Coolants , Cycles , Design , Flow (Dynamics) , Fuels , High temperature , Modeling , Temperature , Thermal hydraulics , Steady state

Thermal Hydraulics and CFD

Linear and Nonlinear Stability Analysis of Molten Salt Natural Circulation Loop

A. K. Srivastava, N. Saikrishna, N. K. Maheshwari

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041401. doi: https://doi.org/10.1115/1.4063040

Abstract

View articletitled, Linear and Nonlinear Stability Analysis of Molten Salt Natural Circulation Loop

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Topics: Stability

Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes

Bikash Pattanayak, Hardik B. Kothadia

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041402. doi: https://doi.org/10.1115/1.4063041

Abstract

View articletitled, Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes

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Topics: Bubbles , Critical heat flux , Dimensions , Pool boiling

Nuclear Safety/Security and Beyond Design Basis Events

Comparative Maps of Safety Features for Fission and Fusion Reactors

Tu Nguyen, Eann A. Patterson, Richard J. Taylor, Y. S. Tseng, Chris Waldon

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041701. doi: https://doi.org/10.1115/1.4062643

Abstract

View articletitled, Comparative Maps of Safety Features for Fission and Fusion Reactors

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Topics: Fusion reactors , Nuclear fission , Safety , Hazards

Plant Systems, O&M, and Life Cycle

Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies

Namgyu Park, Ohjoon Kwon, Youngik Yoo, Taesoon Kim

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041801. doi: https://doi.org/10.1115/1.4062275

Abstract

View articletitled, Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies

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Topics: Deformation , Fuels , Manufacturing , Impact testing , Buckling

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802. doi: https://doi.org/10.1115/1.4062865

Abstract

View articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

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Topics: Errors , Flow (Dynamics) , Instrumentation , Measurement uncertainty , Uncertainty , Nuclear power stations , Sensors , Pipes

Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor

Le Mei, Xiaochun Zhang, Junbao Zhang, Changlei Shao, Jialei Zhu, Ran Huang, Chongzhi Wu

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041803. doi: https://doi.org/10.1115/1.4063008

Abstract

View articletitled, Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor

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Topics: Ferrites (Magnetic materials) , Laser welding , Spent nuclear fuels , Water , Welding , Maintenance , Corrosion , Steel , High pressure (Physics) , Stainless steel

Radiation Science

9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors

Nathan Boyle, Stepan Ozerov, Catalin Harabagiu, Rusi P. Taleyarkhan

ASME J of Nuclear Rad Sci. October 2023, 9(4): 042001. doi: https://doi.org/10.1115/1.4062951

Abstract

View articletitled, 9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors

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Topics: Acoustics , Fluids , Neutrons , Photons , Sensors , Vacuum , Uranium , X-rays

Technical Brief

Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production

Lekhnath Ghimire, Edward Waller

ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501. doi: https://doi.org/10.1115/1.4062644

Abstract

View articletitled, Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production

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Topics: Design , Safety , Small modular reactors , Fuels

Special Papers

Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant

Main Parameters Influencing the Level of Labile Contamination and the Removal Factor

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Hydrogen Loading System for Thin Films for Betavoltaics

Research Papers

Next Generation/Advanced Reactors

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Thermal Hydraulics and CFD

Linear and Nonlinear Stability Analysis of Molten Salt Natural Circulation Loop

Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes

Nuclear Safety/Security and Beyond Design Basis Events

Comparative Maps of Safety Features for Fission and Fusion Reactors

Plant Systems, O&M, and Life Cycle

Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor

Radiation Science

9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors

Technical Brief

Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production

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