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Journal Articles

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Markus Petroff, Rudi Kulenovic, Jörg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041702.
Paper No: NERS-21-1028
https://doi.org/10.1115/1.4051876
Published Online: September 3, 2022
View Article titled, Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection
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Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Test facilities, Water, Flow (Dynamics), Concretes
Journal Articles

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Alain Flores y Flores, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
Paper No: NERS-20-1034
https://doi.org/10.1115/1.4048006
Published Online: May 27, 2022
View Article titled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
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Topics: Explosions, Hydrogen, Aerosols, Thermal hydraulics, Pressure, Flames, Test facilities
Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
https://doi.org/10.1115/1.4052642
Published Online: December 7, 2021
View Article titled, Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
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Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation
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

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility

Octaviana Erawati Fadli, Azizul Khakim, S. Suharyana, A. Suparmi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 032002.
Paper No: NERS-20-1013
https://doi.org/10.1115/1.4048904
Published Online: April 1, 2021
View Article titled, Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO 2 Pin Target at Power Ramp Test Facility
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Topics: Irradiation (Radiation exposure), Safety, Neutron flux, Fuels, Test facilities
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

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.
Paper No: NERS-18-1079
https://doi.org/10.1115/1.4042852
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
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Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)
Journal Articles

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, A. K. Vishnoi, 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. October 2019, 5(4): 041205.
Paper No: NERS-18-1093
https://doi.org/10.1115/1.4043198
Published Online: July 19, 2019
View Article titled, Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor
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Topics: Boiling water reactors, Condensers (steam plant), Coolants, Design, Flow (Dynamics), Heat, Pressure, Safety, Temperature, Test facilities
Journal Articles

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Yongyong Wu, Cheng Ren, Rui Li, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031006.
Paper No: NERS-17-1109
https://doi.org/10.1115/1.4039035
Published Online: May 16, 2018
View Article titled, Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors
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Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity
Journal Articles

Setup of the Supercritical CO 2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

Wolfgang Flaig, Rainer Mertz, Joerg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031004.
Paper No: NERS-17-1121
https://doi.org/10.1115/1.4039595
Published Online: May 16, 2018
View Article titled, Setup of the Supercritical CO 2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System
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Topics: Carbon dioxide, Compressors, Design, Flow (Dynamics), Heat, Heat exchangers, Pressure, Supercritical carbon dioxide, Temperature, Test facilities
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

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Mukesh Kumar, P. K. Verma, A. K. Nayak, A. Rama Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041012.
Paper No: NERS-17-1007
https://doi.org/10.1115/1.4037031
Published Online: July 31, 2017
View Article titled, Experimental Demonstration of AHWR Safety During Prolonged Station Black Out
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Topics: Cooling systems, Design, Heat, Safety, Test facilities, Vessels, Water, Temperature, Fukushima nuclear disaster, Japan, 2011
Journal Articles

An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions

Amir Ali, Edward D. Blandford
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031006.
Paper No: NERS-15-1056
https://doi.org/10.1115/1.4032439
Published Online: June 17, 2016
View Article titled, An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss-of-Coolant Accident Conditions
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Topics: Accidents, Containment, Coolants, Fibers, Flow (Dynamics), Particulate matter, Stability, Testing, Water, Pressurized water reactors
Journal Articles

Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model

Andrea Querol, Sergio Gallardo, Gumersindo Verdú
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021020.
Paper No: NERS-15-1029
https://doi.org/10.1115/1.4031016
Published Online: February 29, 2016
View Article titled, Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled-Up Model
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Topics: Cladding systems (Building), Coolants, Delays, Flow (Dynamics), Pressure, Temperature, Thermocouples, Transients (Dynamics), Steady state, Secondary cells
Journal Articles

Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor

Csaba Maráczy, György Hegyi, István Trosztel, Emese Temesvári
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011004.
Paper No: NERS-15-1041
https://doi.org/10.1115/1.4030933
Published Online: December 9, 2015
View Article titled, Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor
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Topics: Fuels, Nuclear fuels, Safety, Scram, Temperature, Water, Pressure, Steady state, Test facilities, Fuel rods