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Journal Articles

Hydrogen Loading System for Thin Films for Betavoltaics

Darrell Cheu, Thomas Adams, Shripad Revankar

ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.

Paper No: NERS-22-1172

DOI: https://doi.org/10.1115/1.4056974

Published Online: March 13, 2023

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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

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.

Paper No: NERS-22-1036

DOI: https://doi.org/10.1115/1.4056260

Published Online: February 8, 2023

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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

ASME J of Nuclear Rad Sci. July 2023, 9(3): 032001.

Paper No: NERS-22-1038

DOI: https://doi.org/10.1115/1.4056508

Published Online: February 8, 2023

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Topics: Copper, Leakage, Neutrons, Uncertainty, Spectra (Spectroscopy), Neutron sources

Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

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

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1137

DOI: https://doi.org/10.1115/1.4056772

Published Online: January 1, 2023

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Topics: Design, Supercritical carbon dioxide, Coolants, Feedback, Diluents, Fuels, Leakage, Neutrons, Cross section (Physics), Nuclear fission

Journal Articles

On the Self-Shielding in the Unresolved Resonance Range

Daniel Lopez Aldama, Andrej Trkov, Dermott E. Cullen

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041503.

Paper No: NERS-21-1026

DOI: https://doi.org/10.1115/1.4052377

Published Online: March 16, 2022

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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

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.

Paper No: NERS-21-1036

DOI: https://doi.org/10.1115/1.4050770

Published Online: October 19, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.

Paper No: NERS-20-1059

DOI: https://doi.org/10.1115/1.4051364

Published Online: August 12, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.

Paper No: NERS-20-1012

DOI: https://doi.org/10.1115/1.4048477

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.

Paper No: NERS-20-1064

DOI: https://doi.org/10.1115/1.4048764

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.

Paper No: NERS-20-1157

DOI: https://doi.org/10.1115/1.4050207

Published Online: March 10, 2021

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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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501.

Paper No: NERS-20-1017

DOI: https://doi.org/10.1115/1.4048763

Published Online: October 30, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021114.

Paper No: NERS-19-1061

DOI: https://doi.org/10.1115/1.4045225

Published Online: February 5, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107.

Paper No: NERS-19-1028

DOI: https://doi.org/10.1115/1.4045034

Published Online: January 29, 2020

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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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.

Paper No: NERS-17-1237

DOI: https://doi.org/10.1115/1.4045125

Published Online: November 29, 2019

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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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041401.

Paper No: NERS-18-1007

DOI: https://doi.org/10.1115/1.4043294

Published Online: July 19, 2019

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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

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031501.

Paper No: NERS-17-1220

DOI: https://doi.org/10.1115/1.4042115

Published Online: May 3, 2019

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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

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030913.

Paper No: NERS-18-1086

DOI: https://doi.org/10.1115/1.4043378

Published Online: April 19, 2019

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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

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011013.

Paper No: NERS-18-1071

DOI: https://doi.org/10.1115/1.4041691

Published Online: January 24, 2019

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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

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021005.

Paper No: NERS-17-1053

DOI: https://doi.org/10.1115/1.4038899

Published Online: March 5, 2018

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Topics: Accidents, Acoustics, Coolants, Design, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Pipes, Pressure

Journal citation

NARROW

Manuscript

Hydrogen Loading System for Thin Films for Betavoltaics

Long-Term Performance of Semimetallic Gaskets

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

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

On the Self-Shielding in the Unresolved Resonance Range

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

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

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

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

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

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

Testing Oxygen Nuclear Data Libraries in Research Center Rez

Leakage Estimate in Nonuniformly Compressed Packing Rings

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

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

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

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

VVER 1000 Severe Accident Analyses Using MELCOR Code

Evaluation of Interfacial and Permeation Leaks in Gaskets and Compression Packing

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

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