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Journal Articles

Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility

Bhuvaneshwar Gera, Pavan K. Sharma, Aditya Karanam, Shubham Mishra, I. Thangamani, Nandan Saha, Anu Dutta, Priyanshu Goyal, Vishnu Verma, Jayanta Chattopadhyay
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021701.
Paper No: NERS-22-1118
https://doi.org/10.1115/1.4063239
Published Online: October 20, 2023
View Article titled, Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility
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Topics: Containment, Errors, Helium, Hydrogen
Journal Articles

Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011701.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: October 20, 2023
View Article titled, Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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Topics: Accidents, Containment, Ducts, Nuclear power stations, Fluids
Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.
Paper No: NERS-22-1025
https://doi.org/10.1115/1.4055258
Published Online: September 2, 2022
View Article titled, Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU
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Topics: Accidents, Containment, Failure, Pressure, Water
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Matjaž Žvar, Tomaž Žagar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.
Paper No: NERS-21-1022
https://doi.org/10.1115/1.4052013
Published Online: March 16, 2022
View Article titled, Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years
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Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels
Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.
Paper No: NERS-20-1021
https://doi.org/10.1115/1.4050211
Published Online: April 16, 2021
View Article titled, Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis
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Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water
Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.
Paper No: NERS-19-1170
https://doi.org/10.1115/1.4047552
Published Online: September 4, 2020
View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty
Journal Articles

Simulation of the Performance of the Venturi Scrubber for an Advanced Reactor Containment Venting Conditions

Goel Paridhi, K. Nayak Arun
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011201.
Paper No: NERS-18-1118
https://doi.org/10.1115/1.4044845
Published Online: November 29, 2019
View Article titled, Simulation of the Performance of the Venturi Scrubber for an Advanced Reactor Containment Venting Conditions
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Topics: Absorption, Containment, Drops, Pressure, Venturi tubes
Journal Articles

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Milorad B. Dzodzo, Francesco Oriolo, Walter Ambrosini, Marco Ricotti, Davor Grgic, Roberta Ferri, Andrea Achilli, Fosco Bianchi, Paride Meloni
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208.
Paper No: NERS-18-1027
https://doi.org/10.1115/1.4042496
Published Online: September 3, 2019
View Article titled, Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility
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Topics: Containment vessels, Engineering prototypes, Pressure, Reactor vessels, Test facilities, Transients (Dynamics), Water, Design, Heat, Containment
Journal Articles

Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test

Huang Jingyu, Pan Xinxin, Song Chunjing
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031701.
Paper No: NERS-17-1198
https://doi.org/10.1115/1.4042495
Published Online: May 3, 2019
View Article titled, Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test
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Topics: Pressure, Wind, Wind tunnels, Wind velocity, Containment, Cooling systems, Pressurized water reactors, Air flow
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

The AP1000 Plant and the China Project Commissioning Success

Bryan N. Friedman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2019, 5(1): 010302.
Paper No: NERS-18-1106
https://doi.org/10.1115/1.4041973
Published Online: January 24, 2019
View Article titled, The AP1000 Plant and the China Project Commissioning Success
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Topics: China, Safety, Cooling, Containment, Heat, Nuclear power stations, Plant design, Design, Accidents
Journal Articles

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

Kevin Fernández-Cosials, Gonzalo Jiménez, César Serrano, Luisa Ibáñez, Ángel Peinado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031016.
Paper No: NERS-17-1065
https://doi.org/10.1115/1.4038595
Published Online: May 16, 2018
View Article titled, Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
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Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation
Journal Articles

Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions

Laurent Cantrel, Thierry Albiol, Loïc Bosland, Juliette Colombani, Frédéric Cousin, Anne-Cécile Grégoire, Olivia Leroy, Sandrine Morin, Christian Mun, Marie-Noëlle Ohnet, Sidi Souvi, Céline Monsanglant-Louvet, Florent Louis, Bruno Azambre, Christophe Volkringer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020903.
Paper No: NERS-16-1136
https://doi.org/10.1115/1.4038223
Published Online: March 5, 2018
View Article titled, Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions
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Topics: Accidents, Aerosols, Containment, Filters, Irradiation (Radiation exposure), Modeling, Ruthenium, Simulation, Nuclear fission, Nuclear reactor cooling
Journal Articles

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902.
Paper No: NERS-16-1115
https://doi.org/10.1115/1.4038059
Published Online: March 5, 2018
View Article titled, Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes
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Topics: Aerosols, Containment, Nuclear fission, Temperature, Sensitivity analysis, Water, Condensers (steam plant), Thermal hydraulics, Condensation
Journal Articles

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Rafael Bocanegra, Valentino Di Marcello, Victor H. Sánchez-Espinoza, Gonzalo Jiménez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020908.
Paper No: NERS-16-1114
https://doi.org/10.1115/1.4038062
Published Online: March 5, 2018
View Article titled, Fukushima Unit 2 Accident Simulation With MELCOR 2.1
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Topics: Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Pressure, Safety, Simulation, Underground injection, Leakage, Pumps, Flow (Dynamics)
Journal Articles

Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor

Josef Hasslberger, Peter Katzy, Lorenz R. Boeck, Thomas Sattelmayer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041014.
Paper No: NERS-16-1103
https://doi.org/10.1115/1.4037094
Published Online: July 31, 2017
View Article titled, Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor
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Topics: Computational fluid dynamics, Explosions, Flames, Hydrogen, Ignition, Pressure, Pressurized water reactors, Simulation, Combustion, Containment
Journal Articles

Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

Zhifei Yang, Yali Chen, Hu Luo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041011.
Paper No: NERS-16-1109
https://doi.org/10.1115/1.4036892
Published Online: July 31, 2017
View Article titled, Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline
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Topics: Accidents, Drills (Tools), Accident management, Containment, Graphical user interfaces, Industrial research, Safety
Journal Articles

Effects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents

A. C. Morreale, L. S. Lebel, M. J. Brown
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020907.
Paper No: NERS-16-1064
https://doi.org/10.1115/1.4035434
Published Online: March 1, 2017
View Article titled, Effects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents
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Topics: Accidents, Containment, Nuclear fission, Failure, Pressure, Vessels