Volume 7 Issue 2 | ASME J. of Nuclear Rad Sci.

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Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020

Guest Editorial

Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020

Michal Košťál, Martin Schulc

ASME J of Nuclear Rad Sci. April 2021, 7(2): 020301. doi: https://doi.org/10.1115/1.4049945

Extract

View articletitled, Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020

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Topics: Nuclear engineering , Collaboration , Nuclear reactors

Review Article

Improvement of Steels' Corrosion Resistance in Liquid Lead and Lead-Bismuth by Coatings—Review

M. Pazderová, L. Rozumová, L. Košek, A. Hojná

ASME J of Nuclear Rad Sci. April 2021, 7(2): 020801. doi: https://doi.org/10.1115/1.4048631

Abstract

View articletitled, Improvement of Steels' Corrosion Resistance in Liquid Lead and Lead-Bismuth by Coatings—Review

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Topics: Coatings , Corrosion resistance , Steel , Aluminum , Corrosion

Research Papers

Next Generation/Advanced Reactors

European Research Program on Supercritical Water-Cooled Reactor

M. Kryková, T. Schulenberg, M. Arnoult Růžičková, A. Sáez-Maderuelo, I. Otic, S. Czifrus, L. Cizelj, G. L. Pavel

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021301. doi: https://doi.org/10.1115/1.4048901

Abstract

View articletitled, European Research Program on Supercritical Water-Cooled Reactor

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Topics: Design , Safety , Small modular reactors , Supercritical water reactors , Water , Corrosion , Thermal hydraulics , Physics

Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

Marek Ruščák, Tomáš Melichar, Jan Syblík, Otakar Frýbort, David Harut, Evžen Losa, Martin Mareček, Guido Mazzini, Mathieu Reungoat, Jan Pilát, Marek Benčik, Pavel Král

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021302. doi: https://doi.org/10.1115/1.4049715

Abstract

View articletitled, Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

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Topics: Circuits , Heat , Cooling , Fuels , Safety

Thermal Hydraulics and CFD

Flow Analysis in a Steam Turbine Control Valve With Through-Flow Valve Chamber

Vaclav Slama, Lukas Mrozek, Ladislav Tajc, Marek Klimko, Pavel Zitek

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021401. doi: https://doi.org/10.1115/1.4049055

Abstract

View articletitled, Flow Analysis in a Steam Turbine Control Valve With Through-Flow Valve Chamber

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Topics: Diffusers , Flow (Dynamics) , Valves , Pressure

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402. doi: https://doi.org/10.1115/1.4049854

Abstract

View articletitled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

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Topics: Accidents , Coolants , Flow (Dynamics) , Pressure , Safety , Simulation , Water , Nuclear power stations , Feedwater , Design

Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications

Radomír Filip, Tomáš Melichar

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021403. doi: https://doi.org/10.1115/1.4050205

Abstract

View articletitled, Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications

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Topics: Computational fluid dynamics , Flow (Dynamics) , Heat exchangers , Heat transfer , Heat transfer coefficients , Helium , Shells , Temperature , Pressure , Water

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404. doi: https://doi.org/10.1115/1.4050207

Abstract

View articletitled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

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Topics: Flow (Dynamics) , Pressure , Safety , Simulation , Temperature , Transients (Dynamics) , Water , Heat transfer , Pumps , Light water reactors

Reactor Physics

Testing Oxygen Nuclear Data Libraries in Research Center Rez

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Luiz Leal

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501. doi: https://doi.org/10.1115/1.4048763

Abstract

View articletitled, Testing Oxygen Nuclear Data Libraries in Research Center Rez

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Topics: Neutrons , Oxygen , Spectra (Spectroscopy) , Water , Testing , Fuels , Neutron sources , Leakage

Overview of Validation Experiments Focused on Silicon in LR-0

Tomáš Czakoj, Michal Košťál, Tomáš Peltan, Jan Šimon, Roberto Capote

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021502. doi: https://doi.org/10.1115/1.4048480

Abstract

View articletitled, Overview of Validation Experiments Focused on Silicon in LR-0

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Topics: Sands , Silicon , Fuels

Validation of the Fast Neutron Field in the Radial Channel of the VR-1 Reactor

Evžen Losa, Michal Košťál, Milan Štefánik, Jan Šimon, Tomáš Czakoj, Zdeněk Matěj, František Cvachovec, Filip Mravec, Jan Rataj, Ľubomír Sklenka

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021503. doi: https://doi.org/10.1115/1.4048906

Abstract

View articletitled, Validation of the Fast Neutron Field in the Radial Channel of the VR-1 Reactor

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Topics: Neutrons , Fuels

Nuclear Fuels/Cycles and Materials

Methodology for Measurement of Density of Liquid Oxides

Jan Hrbek, Bence Mészáros, Mykhaylo Paukov, Martin Kudláč

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021601. doi: https://doi.org/10.1115/1.4048478

Abstract

View articletitled, Methodology for Measurement of Density of Liquid Oxides

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Topics: Density , Temperature , Electromagnetic induction , High temperature

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

David Rot, Jan Hrbek, Jakub Jirinec

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602. doi: https://doi.org/10.1115/1.4048899

Abstract

View articletitled, Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

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Topics: Aluminum , Cooling , Design , Electromagnetic induction , Heat transfer , Melting , Temperature , Water , Inductors , Heat flux

Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

Jiri Hajek, David Rot, Jana Cubrova, Jakub Jirinec

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021603. doi: https://doi.org/10.1115/1.4048847

Abstract

View articletitled, Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

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Topics: Annealing , Electromagnetic induction , Steel , Temperature , Wire , Heating , Inductors

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604. doi: https://doi.org/10.1115/1.4049053

Abstract

View articletitled, Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

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Topics: Cladding systems (Building) , High temperature , Hydrogen , Nanoindentation , Oxidation , Oxygen , Temperature , Zirconium , Accidents

Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead

Lucia Rozumová, Lukáš Košek, Jan Vít, Anna Hojná, Patricie Halodová

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021605. doi: https://doi.org/10.1115/1.4049719

Abstract

View articletitled, Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead

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Topics: Corrosion , Oxygen , Stainless steel , Steel

Plant Systems, O&M, and Life Cycle

Manipulation System for Measuring Heat Flux in Radioactive Melt

Michal Knedlík, David Rot, Jan Hrbek

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801. doi: https://doi.org/10.1115/1.4048632

Abstract

View articletitled, Manipulation System for Measuring Heat Flux in Radioactive Melt

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Topics: Control algorithms , Electromagnetic induction , Heat flux , Manipulators , Melting , Safety , Temperature , Testing , User interfaces , Computer software

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

Abstract

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

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Topics: Cladding systems (Building) , Coatings , Fuels , Testing , Wear , Wire , Zirconium , Failure , X-rays , Focused ion beams

Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy

J. Patera, J. Jansa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021803. doi: https://doi.org/10.1115/1.4048238

Abstract

View articletitled, Application of Nonlinear Elastic Wave Spectroscopy in the Field of Nuclear Energy

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Topics: Elastic waves , Excitation , Nuclear power , Spectroscopy , Concretes , Microcracks , Pipes , Steel , Concrete beams , Concrete testing

The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

Pavel Kůs, Martin Kronďák, Martin Skala, Alena Kobzová, Petr Brabec, Patricie Halodová, Janka Mihóková, Štefan Tkáč, Anna Černá

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021804. doi: https://doi.org/10.1115/1.4049281

Abstract

View articletitled, The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

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Topics: Circuits , Nuclear power stations , Hydrogen , Magnetite , Water , Microscopy

Radiation Science

Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

Zbyněk Hlaváč, Jaroslava Zatloukalová, Michal Košťál, Evžen Losa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022001. doi: https://doi.org/10.1115/1.4048768

Abstract

View articletitled, Study of a Gamma Radiation Impact on Concrete Properties Under Severe Accident Conditions

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Topics: Concretes , Irradiation (Radiation exposure) , Neutrons , Accidents , Neutron flux , Gamma rays , Radiation (Physics)

Testing and Validation of Nuclear Fuel Composition Using SIMS Method

Ivan Elantyev, Michal Kostal, Evzen Losa, Kristina Sihelska, Klara Rezankova, Jan Lorincik

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022002. doi: https://doi.org/10.1115/1.4049097

Abstract

View articletitled, Testing and Validation of Nuclear Fuel Composition Using SIMS Method

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Topics: Particulate matter , Secondary ion mass spectrometry , Uranium , Fuels , Nuclear fuels , Testing

The Use of Polycarbonate as Dosimeter of High Doses

David Zoul, Markéta Koplová, Vít Rosnecký, Michal Košťál, Miroslav Vinš, Jan Šimon, Martin Schulc, Martin Cabalka, Jan Kučera, Vladimír Strunga

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022003. doi: https://doi.org/10.1115/1.4049717

Abstract

View articletitled, The Use of Polycarbonate as Dosimeter of High Doses

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Topics: Dosimeters , Dosimetry , Irradiation (Radiation exposure) , Neutrons , Radiation (Physics) , Water , Wavelength , Gamma rays , Photons , Nuclear reactors

Neutron Field Shaping Using Graphite for Reaction Rate Measurements

Mikita Sobaleu, Michal Košťál, Jan Šimon, Evžen Losa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022004. doi: https://doi.org/10.1115/1.4049725

Abstract

View articletitled, Neutron Field Shaping Using Graphite for Reaction Rate Measurements

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Topics: Chemical kinetics , Graphite , Irradiation (Radiation exposure) , Neutrons , Uncertainty , Dosimetry

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Vlastimil Juříček, Michal Košťál, Evžen Losa, Tomáš Czakoj, Zdeněk Matěj, František Cvachovec, Martin Schulc, Jan Šimon, Filip Mravec, Václav Přenosil, Vojtěch Rypar

ASME J of Nuclear Rad Sci. April 2021, 7(2): 022005. doi: https://doi.org/10.1115/1.4049726

Abstract

View articletitled, The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

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Topics: Filters , Iron , Neutrons , Silicon , Spectra (Spectroscopy) , Neutron flux , Steel

Technical Briefs

Three-Dimensional Profilometry Utilization on VVER Type Reactors

Jaroslav Brom, Jan Patera, Pavel Zahrádka

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024501. doi: https://doi.org/10.1115/1.4048237

Abstract

View articletitled, Three-Dimensional Profilometry Utilization on VVER Type Reactors

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Topics: Boilers , Reactor vessels , Lasers , Shapes , Nuclear power stations , Water

Comparison of Neutron-Gamma Separation Qualities of Various Organic Scintillation Materials and Liquid Scintillator LSB-200

Zdeněk Matěj, Filip Mravec, Aleš Jančár, Michal Košťál, František Kučera, František Cvachovec, Václav Prenosil, Zdeněk Kopecký, Jiří Čulen, Oldřich Pecák

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024502. doi: https://doi.org/10.1115/1.4048767

Abstract

View articletitled, Comparison of Neutron-Gamma Separation Qualities of Various Organic Scintillation Materials and Liquid Scintillator LSB-200

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Topics: Neutrons , Separation (Technology) , Sensors

Methodology of ⁶³Cu(n,2n)⁶²Cu Reaction Rate Measurement

Martin Schulc, Michal Košťál, Jan Šimon, Evžen Novák

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024503. doi: https://doi.org/10.1115/1.4048236

Abstract

View articletitled, Methodology of <sup>63</sup>Cu(n,2n)<sup>62</sup>Cu Reaction Rate Measurement

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Topics: Half-life , Irradiation (Radiation exposure) , Isotopes , Neutrons , Nuclear fission , Uncertainty , Gamma ray spectrometry , Emissions

Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

J. Veselá, P. Mareš, P. Zahrádka, J. Patera

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024504. doi: https://doi.org/10.1115/1.4048479

Abstract

View articletitled, Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

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Topics: Blades , Fracture (Materials) , Steam turbines , Surface cracks , Testing , Ultrasonic testing , Corrosion , Turbine blades , Magnetic particles , Eddies (Fluid dynamics)