Volume 5 Issue 3 | ASME J. of Nuclear Rad Sci.

Guest Editorial

Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030301. doi: https://doi.org/10.1115/1.4043382

View articletitled, Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Topics: Accidents , Circuits , Coolants , Corrosion , Generation IV reactors , Materials research , Modeling , Nuclear engineering , Nuclear fuel cycle , Nuclear reactors

Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Rod Bow Ultrasonic Measurements Possibilities

Marcin Kopeć, Martina Malá

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030901. doi: https://doi.org/10.1115/1.4041277

Abstract

View articletitled, Rod Bow Ultrasonic Measurements Possibilities

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Topics: Fuel rods , Probes , Inspection , Ultrasonic measurement , Fuels , Radiation (Physics) , Nuclear fuels

Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

Anna Hojna, Fosca Di Gabriele, Michal Chocholousek, Zbynek Spirit, Lucia Rozumova

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030902. doi: https://doi.org/10.1115/1.4041564

Abstract

View articletitled, Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

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Topics: Fracture (Materials) , Polishing , Stress , Steel

Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core

Tomáš Czakoj, Evžen Losa

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030903. doi: https://doi.org/10.1115/1.4041692

Abstract

View articletitled, Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core

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Topics: Tsunamis , Uncertainty

Development of Experimental Instrumentation for Measurement of Advection in Narrow Aperture in Granite Block

Jaroslav Kotowsk, Tomáš Černoušek, Filip Jankovský, Pavel Kůs, Petr Polívka, Martin Skala, Hana Kovářová, Milan Zuna

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030904. doi: https://doi.org/10.1115/1.4041790

Abstract

View articletitled, Development of Experimental Instrumentation for Measurement of Advection in Narrow Aperture in Granite Block

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Topics: Abrasion , Flow (Dynamics) , Instrumentation , Rocks , Tubing , Silicones

The Behavior of Corundum Ceramic in Molten Salt

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Jan Hrbek, Petr Bezdička, Ivona Sedlářová

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030905. doi: https://doi.org/10.1115/1.4042359

Abstract

View articletitled, The Behavior of Corundum Ceramic in Molten Salt

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Topics: Ceramics , Oxidation , Porosity , Weight (Mass) , X-ray diffraction , Organic wastes , Water

Measurement of Selected Differential Cross Sections in ²³⁵U Spectrum

Nicola Burianová, Michal Košt´ál, Martin Schulc, Jan Šimon, Martin Mareček, Jan Uhlíř

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030906. doi: https://doi.org/10.1115/1.4042850

Abstract

View articletitled, Measurement of Selected Differential Cross Sections in 235U Spectrum

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Topics: Chemical kinetics , Computational methods , Cross section (Physics) , Gamma ray spectrometry , Manganese dioxide , Neutrons , Nuclear fission , Sensors , Uncertainty , Irradiation (Radiation exposure)

Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit

Petr Samek, Ondřej Chocholatý, Zdeněk Čančura, Antonín Kříž

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030907. doi: https://doi.org/10.1115/1.4043105

Abstract

View articletitled, Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit

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Topics: Circuits , Coatings , Corrosion , Corrosion resistance , Steel , Welded joints , Testing , Coating processes

Measuring System for Recuperation Units

Jakub Jiřinec, David Rot

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030908. doi: https://doi.org/10.1115/1.4043103

Abstract

View articletitled, Measuring System for Recuperation Units

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Topics: Heat recovery , Optimization , Temperature , Computer software , Control rooms , Measurement systems , Nuclear power stations , Programmable controllers , Space , Suction

Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

Anna Hojna, Mariia Zimina, Lucia Rozumova

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030909. doi: https://doi.org/10.1115/1.4043099

Abstract

View articletitled, Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

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Topics: Fracture (Materials) , Polishing , Pressurized water reactors , Steel , Stress , Water , Fracture (Process) , Testing , Grinding

Corrosion Experiments on Ceramic Samples Within Molten Salts

Jan Hadrava, Vojtěch Galek, Jaroslav Stoklasa, Jan Hrbek, Kateřina Kunešová, Petr Bezdička, Ivona Sedlářová

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030910. doi: https://doi.org/10.1115/1.4043097

Abstract

View articletitled, Corrosion Experiments on Ceramic Samples Within Molten Salts

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Topics: Ceramics , Corrosion , Oxidation , Porosity , Weight (Mass) , X-ray diffraction , Temperature

Preliminary Experiments While Designing a Cold Crucible for Metal Melting

David Rot, Jakub Jiřinec

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030911. doi: https://doi.org/10.1115/1.4043199

Abstract

View articletitled, Preliminary Experiments While Designing a Cold Crucible for Metal Melting

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Topics: Alloys , Computer simulation , Design , Electromagnetic induction , Inductors , Melting , Metals , Stress , Magnetohydrodynamics , Generators

Spatial Spectrum From Particle Image Velocimetry Data

Daniel Duda, Vaclav Uruba

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030912. doi: https://doi.org/10.1115/1.4043319

Abstract

View articletitled, Spatial Spectrum From Particle Image Velocimetry Data

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Topics: Filters , Kinetic energy , Particulate matter , Turbulence , Vortices , Noise (Sound) , Shear (Mechanics) , Errors

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. doi: https://doi.org/10.1115/1.4043378

Abstract

View articletitled, VVER 1000 Severe Accident Analyses Using MELCOR Code

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Topics: Accidents , Containment , Pressure , Water , Temperature , Nuclear fission , Failure , Leakage , Boilers

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

Guido Mazzini, Miloš Kynčl, Marek Ruščák, Miroslav Hrehor, Alis Musa, Antonio Dambrosio, Vincenzo Romanello

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030914. doi: https://doi.org/10.1115/1.4043377

Abstract

View articletitled, Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

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Topics: Helium , Simulation , Steady state , Temperature , Flow (Dynamics) , Compressors , Coolants , Pipes

Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

Michal Košťál, Zdeněk Matěj, Filip Mravec, František Cvachovec, Martin Schulc, Vlastimil Juříček, Vojtěch Rypar, Jaroslav Šoltés, Evžen Losa, Ladislav Viererbl

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030915. doi: https://doi.org/10.1115/1.4043197

Abstract

View articletitled, Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

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Topics: Neutrons , Scintillation counters , Silicon , Spectra (Spectroscopy) , Testing , Neutron beams , Resolution (Optics)

Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios

Guido Mazzini, Tadas Kaliatka, Maria Teresa Porfiri

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030916. doi: https://doi.org/10.1115/1.4043379

Abstract

View articletitled, Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios

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Topics: Accidents , Dust , Plasmas (Ionized gases) , Fusion reactors , Safety , Vessels

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917. doi: https://doi.org/10.1115/1.4043462

Abstract

View articletitled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

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Topics: Alloys , High temperature , Oxidation , Testing , Transparency , Zirconium , Creep , Microscopy , Electron backscatter diffraction , Cladding systems (Building)

Investigation of ¹²⁷I(n,2n)¹²⁶I and ²³Na(n,2n)²²Na Reactions Using ²⁵²Cf Neutron Source

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Nicola Burianová

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030918. doi: https://doi.org/10.1115/1.4039774

Abstract

View articletitled, Investigation of 127I(n,2n)126I and 23Na(n,2n)22Na Reactions Using 252Cf Neutron Source

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Topics: Chemical kinetics , Cross section (Physics) , Emissions , Irradiation (Radiation exposure) , Neutron sources , Neutrons , Uncertainty , Nuclear fission , Sodium , Germanium

Production of Realistic Flaws and Their Meaning for Ultrasonic Testing

Jiri Hodac, Pavel Mares, Jaromir Janousek, Martin Linhart

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030919. doi: https://doi.org/10.1115/1.4042598

Abstract

View articletitled, Production of Realistic Flaws and Their Meaning for Ultrasonic Testing

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Topics: Calibration , Echoes , Fatigue cracks , Ultrasonic testing

Research Papers

Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10⁻⁷ Mass % Dissolved Oxygen

Valentyn Tsisar, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031201. doi: https://doi.org/10.1115/1.4041432

Abstract

View articletitled, Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10−7 Mass % Dissolved Oxygen

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Topics: Corrosion , Oxygen , Steel , Oxidation , Metals

An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems

Huseyin Atilla Ozgener, Ceyhun Yavuz

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031401. doi: https://doi.org/10.1115/1.4042021

Abstract

View articletitled, An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems

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Topics: Diffusion (Physics) , Polishing equipment , Neutron sources , Neutrons , Design

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. doi: https://doi.org/10.1115/1.4042115

Abstract

View articletitled, 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

The Risk of Extended Power Loss and the Probability of Emergency Restoration for Severe Events and Nuclear Accidents

Romney B. Duffey

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031601. doi: https://doi.org/10.1115/1.4042970

Abstract

View articletitled, The Risk of Extended Power Loss and the Probability of Emergency Restoration for Severe Events and Nuclear Accidents

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Topics: Damage , Fire , Probability , Storms , Emergencies , Emergency power , Risk , Fukushima nuclear disaster, Japan, 2011

Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test

Huang Jingyu, Pan Xinxin, Song Chunjing

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031701. doi: https://doi.org/10.1115/1.4042495

Abstract

View articletitled, Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test

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Topics: Pressure , Wind , Wind tunnels , Wind velocity , Containment , Cooling systems , Pressurized water reactors , Air flow

Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031702. doi: https://doi.org/10.1115/1.4042541

Abstract

View articletitled, Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System

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Topics: Clearances (Engineering) , Cylinders , Design , Flow (Dynamics) , Fuels , Hydraulic drive systems , Pressure , Scram , Temperature , Water

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

You Shi, Dong Ning, Yi-zhong Yang

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031901. doi: https://doi.org/10.1115/1.4043096

Abstract

View articletitled, Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

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Topics: Design , Manufacturing , Neutrons , Nuclear power stations , Spent nuclear fuels , Testing , China

Technical Brief

Safety Constraints of Instrumental and Control Algorithm Configuration Based on SCADE Platform

Hua Liu, Xiao-Hua Yang, Zhao-Hui Liu, Shi-Yu Yan, Meng Li, Jie Liu, Zhi Chen

ASME J of Nuclear Rad Sci. July 2019, 5(3): 034501. doi: https://doi.org/10.1115/1.4042704

Abstract

View articletitled, Safety Constraints of Instrumental and Control Algorithm Configuration Based on SCADE Platform

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Topics: Safety , Signals , Algorithms

Guest Editorial

Guest Editorial: Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Rod Bow Ultrasonic Measurements Possibilities

Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core

Development of Experimental Instrumentation for Measurement of Advection in Narrow Aperture in Granite Block

The Behavior of Corundum Ceramic in Molten Salt

Measurement of Selected Differential Cross Sections in ²³⁵U Spectrum

Improvement of Corrosion Resistance of Dissimilar Welded Joints in VVER Secondary Circuit

Measuring System for Recuperation Units

Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

Corrosion Experiments on Ceramic Samples Within Molten Salts

Preliminary Experiments While Designing a Cold Crucible for Metal Melting

Spatial Spectrum From Particle Image Velocimetry Data

VVER 1000 Severe Accident Analyses Using MELCOR Code

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Investigation of ¹²⁷I(n,2n)¹²⁶I and ²³Na(n,2n)²²Na Reactions Using ²⁵²Cf Neutron Source

Production of Realistic Flaws and Their Meaning for Ultrasonic Testing

Research Papers

Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10⁻⁷ Mass % Dissolved Oxygen

An Analytical Solution for the Two-Group Diffusion Theory Analysis of Multiregion Source-Driven Systems

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

The Risk of Extended Power Loss and the Probability of Emergency Restoration for Severe Events and Nuclear Accidents

Large Scale Pressurized Water Reactor Passive Containment Cooling System Wind Tunnel Test

Deceleration Performance and Parameter Influence Analysis of the Control Rod Hydraulic Deceleration Device for Control Rod Hydraulic Drive System

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

Technical Brief

Safety Constraints of Instrumental and Control Algorithm Configuration Based on SCADE Platform

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Guest Editorial

Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

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