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Journal Articles

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, 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
Journal Articles

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041109.
Paper No: NERS-22-1172
https://doi.org/10.1115/1.4056974
Published Online: March 13, 2023
View Article titled, Hydrogen Loading System for Thin Films for Betavoltaics
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Topics: Hydrogen, Palladium, Temperature, Leakage, Pressure drop, Thin films
Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.
Paper No: NERS-22-1036
https://doi.org/10.1115/1.4056260
Published Online: February 8, 2023
View Article titled, Long-Term Performance of Semimetallic Gaskets
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Topics: Gaskets, Graphite, Leakage, Temperature, Relaxation (Physics), High temperature, Weight (Mass), Stress
Journal Articles

Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center

Tomáš Czakoj, Michal Košťál, Martin Schulc, Vojtěch Rypar, Evžen Novák, Evžen Losa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.
Paper No: NERS-22-1038
https://doi.org/10.1115/1.4056508
Published Online: February 8, 2023
View Article titled, Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252 Cf Source in Center
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Topics: Copper, Leakage, Neutrons, Uncertainty, Spectra (Spectroscopy), Neutron sources
Journal Articles

On the Self-Shielding in the Unresolved Resonance Range

Daniel Lopez Aldama, Andrej Trkov, Dermott E. Cullen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041503.
Paper No: NERS-21-1026
https://doi.org/10.1115/1.4052377
Published Online: March 16, 2022
View Article titled, On the Self-Shielding in the Unresolved Resonance Range
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Topics: Cross section (Physics), Resonance, Spectra (Spectroscopy), Probability, Leakage
Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.
Paper No: NERS-21-1036
https://doi.org/10.1115/1.4050770
Published Online: October 19, 2021
View Article titled, Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
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Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Article titled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.
Paper No: NERS-20-1059
https://doi.org/10.1115/1.4051364
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
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Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
https://doi.org/10.1115/1.4048477
Published Online: March 16, 2021
View Article titled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
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Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors
Journal Articles

Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

Muhammad Imron, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.
Paper No: NERS-20-1064
https://doi.org/10.1115/1.4048764
Published Online: March 16, 2021
View Article titled, Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
Open the PDF for Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES in another window
Topics: Boron, Coordinate measuring machines, Cross section (Physics), Fuels, Manufacturing, Pressurized water reactors, Transients (Dynamics), Temperature, Diffusion (Physics), Geometry
Journal Articles

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.
Paper No: NERS-20-1157
https://doi.org/10.1115/1.4050207
Published Online: March 10, 2021
View Article titled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors
Journal Articles

Testing Oxygen Nuclear Data Libraries in Research Center Rez

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Luiz Leal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501.
Paper No: NERS-20-1017
https://doi.org/10.1115/1.4048763
Published Online: October 30, 2020
View Article titled, Testing Oxygen Nuclear Data Libraries in Research Center Rez
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Topics: Neutrons, Oxygen, Spectra (Spectroscopy), Water, Testing, Fuels, Neutron sources, Leakage
Journal Articles

Leakage Estimate in Nonuniformly Compressed Packing Rings

Ali Salah Omar Aweimer, Abdel-Hakim Bouzid, Zijian Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021114.
Paper No: NERS-19-1061
https://doi.org/10.1115/1.4045225
Published Online: February 5, 2020
View Article titled, Leakage Estimate in Nonuniformly Compressed Packing Rings
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Topics: Leakage, Packing (Shipments), Packings (Cushioning), Stress, Compression, Pressure, Valves, Porosity, Helium
Journal Articles

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107.
Paper No: NERS-19-1028
https://doi.org/10.1115/1.4045034
Published Online: January 29, 2020
View Article titled, External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
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Topics: Accidents, Coolants, Cooling, Diesel engines, Emergencies, Flow (Dynamics), Hazards, Heat, Leakage, Pressure
Journal Articles

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.
Paper No: NERS-17-1237
https://doi.org/10.1115/1.4045125
Published Online: November 29, 2019
View Article titled, Experimental Investigation on Flash Evaporation Related to Pipe Leakage
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Topics: Evaporation, Flow (Dynamics), High temperature, Leakage, Pipes, Pressure, Sensors, Sprays, Temperature, Temperature distribution
Journal Articles

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

Manish Kumar, Om Pal Singh
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041401.
Paper No: NERS-18-1007
https://doi.org/10.1115/1.4043294
Published Online: July 19, 2019
View Article titled, A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media
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Topics: Neutrons, Waves, Nuclides, Buckling, Leakage, Transients (Dynamics)
Journal Articles

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031501.
Paper No: NERS-17-1220
https://doi.org/10.1115/1.4042115
Published Online: May 3, 2019
View Article titled, Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC
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Topics: Failure, Fracture (Materials), Leakage, Pipes, Probability, Nondestructive evaluation, Stress
Journal Articles

VVER 1000 Severe Accident Analyses Using MELCOR Code

Marek Ruščák, Guido Mazzini, Milos Kynčl, Sevastyan Savanyuk, Miroslav Hrehor, Alis Musa, Alain Flores y Flores
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030913.
Paper No: NERS-18-1086
https://doi.org/10.1115/1.4043378
Published Online: April 19, 2019
View Article titled, VVER 1000 Severe Accident Analyses Using MELCOR Code
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Topics: Accidents, Containment, Pressure, Water, Temperature, Nuclear fission, Failure, Leakage, Boilers
Journal Articles

Evaluation of Interfacial and Permeation Leaks in Gaskets and Compression Packing

Ali Salah Omar Aweimer, Abdel-Hakim Bouzid
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011013.
Paper No: NERS-18-1071
https://doi.org/10.1115/1.4041691
Published Online: January 24, 2019
View Article titled, Evaluation of Interfacial and Permeation Leaks in Gaskets and Compression Packing
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Topics: Gaskets, Leakage, Packing (Shipments), Packings (Cushioning), Stress, Finishes
Journal Articles

Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

Mukesh Kumar, A. K. Nayak, Sumit V. Prasad, P. K. Verma, R. K. Singh, Vikas Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021005.
Paper No: NERS-17-1053
https://doi.org/10.1115/1.4038899
Published Online: March 5, 2018
View Article titled, Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
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Topics: Accidents, Acoustics, Coolants, Design, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Pipes, Pressure