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Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Accepted Manuscript
Armando Nava Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: September 13, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Computers, Fuels, Manufacturing, Nuclear fuels, Nuclear industry, Supercritical fluids, Water
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.
Paper No: NERS-21-1022
https://doi.org/10.1115/1.4052013
Published Online: March 16, 2022
View Article titled, Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years
Open the PDF for Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years in another window
Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels
Journal Articles

Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results

Emil Fridman, Francisco Álvarez Velarde, Pablo Romojaro Otero, Haileyesus Tsige-Tamirat, Antonio Jiménez Carrascosa, Nuria García Herranz, Franck Bernard, Robert Gregg, Una Davies, Jiri Krepel, Simone Massara, Sandra Poumerouly, Enrico Girardi, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011301.
Paper No: NERS-20-1056
https://doi.org/10.1115/1.4048905
Published Online: July 20, 2021
View Article titled, Neutronic Analysis of the European Sodium Fast Reactor: Part I—Fresh Core Results
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Topics: Modeling, Safety, Scram, Sodium, Sodium fast reactors, Temperature, Fuels, Design, Computers, Equilibrium (Physics)
Journal Articles

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102.
Paper No: NERS-18-1130
https://doi.org/10.1115/1.4045030
Published Online: November 8, 2019
View Article titled, A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette
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Topics: Computers, Errors, Fluence (Radiation measurement), Geometry, Neutrons, Particulate matter, Phase space, Photons, Weight (Mass), Dosimeters
Journal Articles

Functional Information of System Components Influenced by Counteractions on Computer-Based Procedure

Tulis Jojok Suryono, Akio Gofuku
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2018, 4(4): 044501.
Paper No: NERS-17-1186
https://doi.org/10.1115/1.4040366
Published Online: September 10, 2018
View Article titled, Functional Information of System Components Influenced by Counteractions on Computer-Based Procedure
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Topics: Computers, Flow (Dynamics), Modeling, Pressurized water reactors, Safety, Emergencies, Accidents, Emergency core cooling systems, Control rooms, Nuclear power stations
Journal Articles

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Thambiayah Nitheanandan, X. Cao, J.-H. Choi, D. Dupleac, D.-H. Kim, H. G. Lele, A. K. Nayak, H. P. Rammohan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.
Paper No: NERS-16-1084
https://doi.org/10.1115/1.4035726
Published Online: March 1, 2017
View Article titled, Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
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Topics: Accidents, Heat, Vessels, Water, Heavy water reactors, Computers, Pressure, Fuels, Containment, Boilers
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2017, 3(2): 024501.
Paper No: NERS-16-1063
https://doi.org/10.1115/1.4035690
Published Online: March 1, 2017
View Article titled, Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea
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Topics: Accidents, Containment, Heavy water reactors, Overpressure protection, Safety, Heat, Design, Computers
Journal Articles

U233 Data Evaluation for Criticality Study

Mohammad Alrwashdeh, Wang Kan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2016, 2(3): 034501.
Paper No: NERS-15-1118
https://doi.org/10.1115/1.4032814
Published Online: June 17, 2016
View Article titled, U233 Data Evaluation for Criticality Study
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Topics: Bayes methods, Computers, Cross section (Physics), Databases, Fittings, Thermal energy, Nuclear fission, Computer software, Neutrons
Journal Articles

RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout

Andrej Prošek, Andrija Volkanovski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041016.
Paper No: NERS-15-1028
https://doi.org/10.1115/1.4030834
Published Online: September 3, 2015
View Article titled, RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout
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Topics: Flow (Dynamics), Pumps, Safety, Computers, Delays, Pressurized water reactors, Probability, Failure, Pressure, Water