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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
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

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Gerard R. Lekhema, Willem A. Cronje, Ian Korir
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802.
Paper No: NERS-19-1062
https://doi.org/10.1115/1.4046353
Published Online: May 27, 2022
View Article titled, High Reliability Microgrid for a Nuclear Facility Emergency Power Supply
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Topics: Microgrids, Reliability, Batteries, Diesel generators, Failure, Risk-based design, Emergency power, Probability, Nuclear power stations
Journal Articles

Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

S. Ehster, L. Ammirabile, E. Bubelis, B. Carluec, J. B. Droin, E. 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): 011304.
Paper No: NERS-20-1078
https://doi.org/10.1115/1.4050766
Published Online: August 3, 2021
View Article titled, Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors
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Topics: Failure, Safety, Heat, Sodium fast reactors, Design, Defense industry, Performance, Accidents
Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.
Paper No: NERS-20-1093
https://doi.org/10.1115/1.4048239
Published Online: November 16, 2020
View Article titled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application
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Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams
Journal Articles

Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

Andrew Oussoren, Paul Chan, Diane Wowk, Andrew Prudil
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.
Paper No: NERS-19-1018
https://doi.org/10.1115/1.4048120
Published Online: October 5, 2020
View Article titled, Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths
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Topics: Failure, Fracture (Materials), Fuels, Nuclear fission, Diffusion (Physics)
Journal Articles

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.
Paper No: NERS-19-1161
https://doi.org/10.1115/1.4047113
Published Online: September 4, 2020
View Article titled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors
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Topics: Design, Diffusion (Physics), Heat exchangers, High temperature, Reliability, Testing, Construction, ASME Standards, ASME Boiler and Pressure Vessel Code, Stress
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

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802.
Paper No: NERS-17-1277
https://doi.org/10.1115/1.4046262
Published Online: May 5, 2020
View Article titled, Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems
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Topics: Computer software, Failure, Instrumentation, Modeling, Nuclear power stations, Safety, Control systems, Hardware, Three-dimensional modeling
Journal Articles

Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method

Edward Shitsi, Emmanuel K. Boafo, Felix Ameyaw, H. C. Odoi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801.
Paper No: NERS-19-1117
https://doi.org/10.1115/1.4045803
Published Online: March 9, 2020
View Article titled, Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method
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Topics: Failure, Feedwater, High pressure (Physics), Pumps, Safety, Valves, Nuclear power stations
Journal Articles

Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service

M. Karam
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011801.
Paper No: NERS-19-1014
https://doi.org/10.1115/1.4044750
Published Online: November 29, 2019
View Article titled, Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service
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Topics: Accidents, Design, Earthquakes, Safety, Pressure, Fuels, Failure, Hazards, Heat
Journal Articles

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601.
Paper No: NERS-18-1080
https://doi.org/10.1115/1.4043108
Published Online: July 19, 2019
View Article titled, Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident
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Topics: Accidents, Heat, Heavy water reactors, Temperature, Vessels, Water, Design, Boiling, Nuclear power stations, Failure
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

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Wentao Li, Danying Gu, Henan Zhang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041011.
Paper No: NERS-17-1290
https://doi.org/10.1115/1.4040888
Published Online: September 10, 2018
View Article titled, Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant
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Topics: Control systems, Event history analysis, Failure, Failure mechanisms, Feedwater, Nuclear power stations, Probability, Reliability
Journal Articles

The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident

Jianfeng Mao, Shiyi Bao, Zhiming Lu, Lijia Luo, Zengliang Gao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041015.
Paper No: NERS-17-1254
https://doi.org/10.1115/1.4040494
Published Online: September 10, 2018
View Article titled, The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
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Topics: Accidents, Creep, Damage, Failure, Finite element analysis, Reactor vessels, Safety, Temperature, Wall thickness, Stress
Journal Articles

Risk Analysis of Spent Fuel Pool Caused by Seismic Events

Ming Wang, Modi Lin, Jinkai Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041012.
Paper No: NERS-17-1273
https://doi.org/10.1115/1.4040367
Published Online: September 10, 2018
View Article titled, Risk Analysis of Spent Fuel Pool Caused by Seismic Events
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Topics: Earthquakes, Spent nuclear fuels, Failure, Accidents, Risk
Journal Articles

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Zhang Donghui, Xiong Wenbin, Li Huwei, Wu Mingyu, Wang Xinzhe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.
Paper No: NERS-17-1272
https://doi.org/10.1115/1.4040029
Published Online: September 10, 2018
View Article titled, Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Fuel rods, Isotopes, Heat transfer, Failure, Cladding systems (Building), Design
Journal Articles

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

Yuki Honda, Hiroyuki Sato, Shigeaki Nakagawa, Hirofumi Ohashi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031013.
Paper No: NERS-17-1253
https://doi.org/10.1115/1.4039066
Published Online: May 16, 2018
View Article titled, Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
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Topics: Accidents, Fuels, Temperature, Uncertainty, Uncertainty analysis, Very high temperature reactors, Heat, Failure
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
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