Search Results | ASME J. of Nuclear Rad Sci.

1-20 of 32

Sort by

Sort Order Select

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

View Article

Topics: Accidents, Containment, Failure, Pressure, Water

Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

DOI: https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

View Article

Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Journal Articles

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Gerard R. Lekhema, Willem A. Cronje, Ian Korir

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802.

Paper No: NERS-19-1062

DOI: https://doi.org/10.1115/1.4046353

Published Online: May 27, 2022

View Article

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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011304.

Paper No: NERS-20-1078

DOI: https://doi.org/10.1115/1.4050766

Published Online: August 3, 2021

View Article

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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.

Paper No: NERS-20-1093

DOI: https://doi.org/10.1115/1.4048239

Published Online: November 16, 2020

View Article

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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.

Paper No: NERS-19-1018

DOI: https://doi.org/10.1115/1.4048120

Published Online: October 5, 2020

View Article

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

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106.

Paper No: NERS-19-1161

DOI: https://doi.org/10.1115/1.4047113

Published Online: September 4, 2020

View Article

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

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

View Article

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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802.

Paper No: NERS-17-1277

DOI: https://doi.org/10.1115/1.4046262

Published Online: May 5, 2020

View Article

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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031801.

Paper No: NERS-19-1117

DOI: https://doi.org/10.1115/1.4045803

Published Online: March 9, 2020

View Article

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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011801.

Paper No: NERS-19-1014

DOI: https://doi.org/10.1115/1.4044750

Published Online: November 29, 2019

View Article

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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601.

Paper No: NERS-18-1080

DOI: https://doi.org/10.1115/1.4043108

Published Online: July 19, 2019

View Article

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

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

View Article

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

View Article

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041011.

Paper No: NERS-17-1290

DOI: https://doi.org/10.1115/1.4040888

Published Online: September 10, 2018

View Article

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041015.

Paper No: NERS-17-1254

DOI: https://doi.org/10.1115/1.4040494

Published Online: September 10, 2018

View Article

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041012.

Paper No: NERS-17-1273

DOI: https://doi.org/10.1115/1.4040367

Published Online: September 10, 2018

View Article

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.

Paper No: NERS-17-1272

DOI: https://doi.org/10.1115/1.4040029

Published Online: September 10, 2018

View Article

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

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031013.

Paper No: NERS-17-1253

DOI: https://doi.org/10.1115/1.4039066

Published Online: May 16, 2018

View Article

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

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

View Article

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

Journal citation

NARROW

Manuscript

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

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

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

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

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

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

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

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

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

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

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

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

VVER 1000 Severe Accident Analyses Using MELCOR Code

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

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

Risk Analysis of Spent Fuel Pool Caused by Seismic Events

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

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

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

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only