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Keywords: Beyond design basis events
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Journal Articles

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

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
... quantitative and qualitative input variables on the figures of merit. 1 Corresponding author. e-mail:  heribertosanchez7@hotmail.com 27 02 2022 30 06 2022 22 04 2024 hydrogen production beyond design basis events nuclear engineering short-term station blackout...
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
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
... water reactor BARC = Bhabha Atomic Research Centre BDBE = beyond design basis event BWR = boiling water reactor ECCS = emergency core cooling system FCVS = filtered containment vent system FOAK = first of a kind feature GDWP = gravity driven water pool ICs...
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

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

X. Gaus-Liu, A. Miassoedov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031003.
Paper No: NERS-16-1107
https://doi.org/10.1115/1.4035853
Published Online: May 25, 2017
... distribution in one horizontal level is asymmetric. For instance, the azimuthal deviation of the heat flux near melt surface was ∼6%. Fig. 9 Normalized heat flux distribution through vessel wall in LIVE 3D tests Advanced reactors Beyond design basis events Current reactors Nuclear safety...
View Article titled, Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head
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Topics: Boundary-value problems, Cooling, Heat flux, Heat transfer, Temperature, Vessels, Geometry, Insulation, Water
Journal Articles

Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition

A. K. Dureja, P. Seshu, D. N. Pawaskar, R. K. Sinha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020905.
Paper No: NERS-16-1093
https://doi.org/10.1115/1.4035784
Published Online: March 1, 2017
..., 2016; published online March 1, 2017. Assoc. Editor: Arun Nayak. 26 08 2016 17 12 2016 Advanced reactors Beyond design basis events At the current stage of the Indian nuclear program, 220/540 MW el horizontal pressure tube type pressurized heavy water reactors (PHWRs...
View Article titled, Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition
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Topics: Contact resistance, Coolants, Deformation, Heat, Heavy water reactors, Manufacturing, Pressure, Temperature, Thermomechanics, Flow (Dynamics)
Journal Articles

Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications

Rusi P. Taleyarkhan, Jeffrey A. Webster, Anthony Sansone, Brian C. Archambault, Randall Reames, Colin D. West
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011004.
Paper No: NERS-15-1176
https://doi.org/10.1115/1.4034975
Published Online: December 20, 2016
... August 13, 2016; final manuscript received September 10, 2016; published online December 20, 2016. Assoc. Editor: Jay F. Kunze. 13 8 2016 10 9 2016 10 9 2016 Alternative energy sources Beyond design basis events Instrumentation Nuclear safety Radiation science Radiation...
View Article titled, Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications
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Topics: Cavitation, Fluids, Glass, Radiation (Physics), Testing, Water, Safety, Pressure, Tension, Nuclear engineering