Journal of Nuclear Engineering and Radiation Science: Recent submissions

Now showing items 301-320 of 913

    • Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods 

      Veselá, J.; Mareš, P.; Zahrádka, P.; Patera, J. (The American Society of Mechanical Engineers (ASME), 2020)
      This article describes methods suitable for crack detection on low pressure steam turbine blades, not including the blade root. These cracks, which are initiated in the corrosion pitting, can cause serious damage to the ...

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

      Schulc, Martin; Košťál, Michal; Šimon, Jan; Novák, Evžen (The American Society of Mechanical Engineers (ASME), 2020)
      This paper presents the measurement of the spectrum-averaged cross section (SACS) of 63Cu(n,2n)62Cu reaction in 252Cf spontaneous fission neutron spectrum. The SACS in the 252Cf spectrum was chosen as a validation tool ...

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

      Matěj, Zdeněk; Mravec, Filip; Jančár, Aleš; Košťál, Michal; Kučera, František; Cvachovec, František; Prenosil, Václav; Kopecký, Zdeněk; Čulen, Jiří; Pecák, Oldřich (The American Society of Mechanical Engineers (ASME), 2020)
      In this work, we compare the pulse-shape discrimination (PSD) properties of newly developed liquid scintillator LSB-200, EJ-299-33A, BC-501A, stilbene, p-terphenyl, and Hidex Aqualight in neutron field generated by the ...

    • Three-Dimensional Profilometry Utilization on VVER Type Reactors 

      Brom, Jaroslav; Patera, Jan; Zahrádka, Pavel (The American Society of Mechanical Engineers (ASME), 2020)
      The paper is focused on the application of three-dimensional (3D) profilometry on water–water energetic reactor (VVER) type nuclear power plant (NPP) equipment. This method is becoming increasingly used in the power industry ...

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

      Juříček, Vlastimil; Košťál, Michal; Losa, Evžen; Czakoj, Tomáš; Matěj, Zdeněk; Cvachovec, František; Schulc, Martin; Šimon, Jan; Mravec, Filip; Přenosil, Václav; Rypar, Vojtěch (The American Society of Mechanical Engineers (ASME), 2021)
      This paper summarizes the issue of the validation of the silicon-filtered neutron beam transport in the deep neutron transport penetration experiment in iron. Iron is an essential structural material important for nuclear ...

    • Neutron Field Shaping Using Graphite for Reaction Rate Measurements 

      Sobaleu, Mikita; Košťál, Michal; Šimon, Jan; Losa, Evžen (The American Society of Mechanical Engineers (ASME), 2021)
      Neutron field shaping is the suitable method for validation of cross section in various energy regions. By increasing the share of neutrons of a certain energy interval and decreasing the share of other, a reaction becomes ...

    • The Use of Polycarbonate as Dosimeter of High Doses 

      Zoul, David; Koplová, Markéta; Rosnecký, Vít; Košťál, Michal; Vinš, Miroslav; Šimon, Jan; Schulc, Martin; Cabalka, Martin; Kučera, Jan; Strunga, Vladimír (The American Society of Mechanical Engineers (ASME), 2021)
      Dosimetry of high doses of ionizing radiation is a method widely used not only in the field of basic and applied research but also in various industries. High-dose irradiation is used in the sterilization of foodstuffs and ...

    • Testing and Validation of Nuclear Fuel Composition Using SIMS Method 

      Elantyev, Ivan; Kostal, Michal; Losa, Evzen; Sihelska, Kristina; Rezankova, Klara; Lorincik, Jan (The American Society of Mechanical Engineers (ASME), 2021)
      Correct mathematical models of a reactor core in benchmarking of reactor physics experiments require detailed knowledge of exact isotopic composition of fuel pellets, especially the presence of neutron absorbers. Among ...

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

      Hlaváč, Zbyněk; Zatloukalová, Jaroslava; Košťál, Michal; Losa, Evžen (The American Society of Mechanical Engineers (ASME), 2020)
      Concrete is an important structural material used in nuclear power plant (NPP) design. Due to relatively high amount of hydrogen as well as the presence of heavier elements, it also acts as a biological shielding. One of ...

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

      Kůs, Pavel; Kronďák, Martin; Skala, Martin; Kobzová, Alena; Brabec, Petr; Halodová, Patricie; Mihóková, Janka; Tkáč, Štefan; Černá, Anna (The American Society of Mechanical Engineers (ASME), 2021)
      The presented article outlines and describes the processes involved in the creation and testing of the passivation layer that was created during hot functional tests (HFTs) at the third unit of the nuclear power plant (NPP) ...

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

      Patera, J.; Jansa, J. (The American Society of Mechanical Engineers (ASME), 2020)
      In the field of nuclear energy, two particular applications are considered—the measurement of biological shielding concrete and measurement of high-temperature high-pressure piping. For the measurement of biological shielding ...

    • On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application 

      Kopeć, Marcin; Pašta, Ondřej; Malá, Martina; Halodová, Patricie; Cvrček, Ladislav; Krejčí, Jakub (The American Society of Mechanical Engineers (ASME), 2020)
      The fretting phenomenon was responsible for over 50% of fuel failure cases in the years 2010–2015 according to International Atomic Energy Agency (IAEA). It shows the scale of the problem for the nuclear power generation ...

    • Manipulation System for Measuring Heat Flux in Radioactive Melt 

      Knedlík, Michal; Rot, David; Hrbek, Jan (The American Society of Mechanical Engineers (ASME), 2020)
      This article is focused on introducing of the manipulation system, which is used to insert equipment or measuring probes into the chamber of a cold crucible during experimental induction skull melting. The measuring probe ...

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

      Rozumová, Lucia; Košek, Lukáš; Vít, Jan; Hojná, Anna; Halodová, Patricie (The American Society of Mechanical Engineers (ASME), 2021)
      Development of liquid lead cooled nuclear systems requires consideration of compatibility issues with the construction materials. In order to understand the corrosion or passivation behavior of the 316 L austenitic stainless ...

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

      Gávelová, Petra; Halodová, Patricie; Marušáková, Daniela; Libera, Ondřej; Krejčí, Jakub; Vrtílková, Věra (The American Society of Mechanical Engineers (ASME), 2020)
      Zirconium-based alloys are one of the most significant materials in thermal-neutron reactor systems. With very low neutron capture cross section, good corrosion resistance, mechanical strength and resistance to neutron ...

    • Induction Annealing of Austenitic Spring Steels for Nuclear Reactors 

      Hajek, Jiri; Rot, David; Cubrova, Jana; Jirinec, Jakub (The American Society of Mechanical Engineers (ASME), 2020)
      This paper describes designing and experimental trials of an induction annealing method for AISI 321H austenitic steel wires. Specifically, it explores the feasibility of incorporating an existing frequency controller into ...

    • Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible 

      Rot, David; Hrbek, Jan; Jirinec, Jakub (The American Society of Mechanical Engineers (ASME), 2020)
      This article aims to explain the mechanism of heat transfer between melt and cold crucible (CC) in processes referred to as induction skull melting (ISM). Several experiments were performed for this purpose. In these ...

    • Methodology for Measurement of Density of Liquid Oxides 

      Hrbek, Jan; Mészáros, Bence; Paukov, Mykhaylo; Kudláč, Martin (The American Society of Mechanical Engineers (ASME), 2020)
      Measurement of physical properties of materials in extreme conditions, such as high temperature, is limited by technological challenges. Nevertheless, modeling of several phenomena relies on the existence of experimental ...

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

      Losa, Evžen; Košťál, Michal; Štefánik, Milan; Šimon, Jan; Czakoj, Tomáš; Matěj, Zdeněk; Cvachovec, František; Mravec, Filip; Rataj, Jan; Sklenka, Ľubomír (The American Society of Mechanical Engineers (ASME), 2020)
      This work aims to characterize the neutron spectrum in the beam going out of the university research reactor (VR-1) using tubular-type of the nuclear fuel, version 4M (IRT-4M) fuel. Thanks to its variability, the core is ...

    • Overview of Validation Experiments Focused on Silicon in LR-0 

      Czakoj, Tomáš; Košťál, Michal; Peltan, Tomáš; Šimon, Jan; Capote, Roberto (The American Society of Mechanical Engineers (ASME), 2020)
      Silicon dioxide is a common material in nature and is also often used in the nuclear industry (concrete, radioactive waste repositories in bedrocks), therefore, properly characterizing neutronic properties is very important ...