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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

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.

Paper No: NERS-22-1025

DOI: https://doi.org/10.1115/1.4055258

Published Online: September 2, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.

Paper No: NERS-21-1073

DOI: https://doi.org/10.1115/1.4052014

Published Online: May 26, 2022

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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

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.

Paper No: NERS-21-1022

DOI: https://doi.org/10.1115/1.4052013

Published Online: March 16, 2022

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.

Paper No: NERS-20-1021

DOI: https://doi.org/10.1115/1.4050211

Published Online: April 16, 2021

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.

Paper No: NERS-19-1164

DOI: https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

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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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.

Paper No: NERS-19-1170

DOI: https://doi.org/10.1115/1.4047552

Published Online: September 4, 2020

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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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011201.

Paper No: NERS-18-1118

DOI: https://doi.org/10.1115/1.4044845

Published Online: November 29, 2019

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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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208.

Paper No: NERS-18-1027

DOI: https://doi.org/10.1115/1.4042496

Published Online: September 3, 2019

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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

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031701.

Paper No: NERS-17-1198

DOI: https://doi.org/10.1115/1.4042495

Published Online: May 3, 2019

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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

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

The AP1000 Plant and the China Project Commissioning Success

Bryan N. Friedman

ASME J of Nuclear Rad Sci. January 2019, 5(1): 010302.

Paper No: NERS-18-1106

DOI: https://doi.org/10.1115/1.4041973

Published Online: January 24, 2019

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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

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031016.

Paper No: NERS-17-1065

DOI: https://doi.org/10.1115/1.4038595

Published Online: May 16, 2018

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Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation

Journal Articles

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

Bruno Gonfiotti, Sandro Paci

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902.

Paper No: NERS-16-1115

DOI: https://doi.org/10.1115/1.4038059

Published Online: March 5, 2018

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Topics: Aerosols, Containment, Nuclear fission, Temperature, Sensitivity analysis, Water, Condensers (steam plant), Thermal hydraulics, Condensation

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

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020903.

Paper No: NERS-16-1136

DOI: https://doi.org/10.1115/1.4038223

Published Online: March 5, 2018

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Topics: Accidents, Aerosols, Containment, Filters, Irradiation (Radiation exposure), Modeling, Ruthenium, Simulation, Nuclear fission, Nuclear reactor cooling

Journal Articles

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Rafael Bocanegra, Valentino Di Marcello, Victor H. Sánchez-Espinoza, Gonzalo Jiménez

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020908.

Paper No: NERS-16-1114

DOI: https://doi.org/10.1115/1.4038062

Published Online: March 5, 2018

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Topics: Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Pressure, Safety, Simulation, Underground injection, Leakage, Pumps, Flow (Dynamics)

Journal Articles

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

Zhifei Yang, Yali Chen, Hu Luo

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041011.

Paper No: NERS-16-1109

DOI: https://doi.org/10.1115/1.4036892

Published Online: July 31, 2017

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Topics: Accidents, Drills (Tools), Accident management, Containment, Graphical user interfaces, Industrial research, Safety

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

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041014.

Paper No: NERS-16-1103

DOI: https://doi.org/10.1115/1.4037094

Published Online: July 31, 2017

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Topics: Computational fluid dynamics, Explosions, Flames, Hydrogen, Ignition, Pressure, Pressurized water reactors, Simulation, Combustion, Containment

Journal Articles

Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR

Rajee Guptan, A. K. Vijaya, Vibha Hari, Rajeev Nama

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020910.

Paper No: NERS-16-1074

DOI: https://doi.org/10.1115/1.4035783

Published Online: March 1, 2017

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Topics: Accidents, Containment, Failure, Safety, Probabilistic safety assessment, Accident management, Radioisotopes

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

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020907.

Paper No: NERS-16-1064

DOI: https://doi.org/10.1115/1.4035434

Published Online: March 1, 2017

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Topics: Accidents, Containment, Nuclear fission, Failure, Pressure, Vessels

Journal Articles

Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea

Y. M. Song, D. H. Kim, S. Y. Park, J. H. Song

ASME J of Nuclear Rad Sci. April 2017, 3(2): 024501.

Paper No: NERS-16-1063

DOI: https://doi.org/10.1115/1.4035690

Published Online: March 1, 2017

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Topics: Accidents, Containment, Heavy water reactors, Overpressure protection, Safety, Heat, Design, Computers

Journal citation

NARROW

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

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

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

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

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

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

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

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

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

VVER 1000 Severe Accident Analyses Using MELCOR Code

The AP1000 Plant and the China Project Commissioning Success

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

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

Research Works on Iodine and Ruthenium Behavior in Severe Accident Conditions

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

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

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

Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR

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

Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea

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