Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 321-340 of 913
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Testing Oxygen Nuclear Data Libraries in Research Center Rez
(The American Society of Mechanical Engineers (ASME), 2020)Oxygen belongs to the group of the most important isotopes in the nuclear data field. The aim of this paper is validate various oxygen nuclear data libraries in different scenarios with high content of oxygen. For this ... -
Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
(The American Society of Mechanical Engineers (ASME), 2021)Supercritical water (SCW) has advantages like high thermal efficiency and can operate at high temperature and pressure. At the same time, however, these properties bring up related issues, such as material compatibility ... -
Numerical Analysis of Heat Transfer on the Shell Side of a Helically Coiled Tube Heat Exchanger for Helium Applications
(The American Society of Mechanical Engineers (ASME), 2021)A new heat transfer correlation for high temperature helium on the shell side of a helically coiled tube heat exchanger was derived with the use of computational fluid dynamics (CFD) tools. The use of suitable heat transfer ... -
Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
(The American Society of Mechanical Engineers (ASME), 2021)After the Fukushima DAIICHI accident, new safety requirements were imposed in order to reduce risk of severe accident. One of the principles that have been adopted is the introduction of emergency action levels resulting ... -
Flow Analysis in a Steam Turbine Control Valve With Through-Flow Valve Chamber
(The American Society of Mechanical Engineers (ASME), 2021)A nuclear power plant also includes a secondary cycle, which main component is a steam turbine. The steam turbine processes the thermal and pressure energy of steam and converts it into mechanical energy. Reliable and safe ... -
Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts
(The American Society of Mechanical Engineers (ASME), 2021)In this paper is described the concept of a 20 MW microreactor cooled by molten salts with the registered trademark of Energy Well. Energy Well reactor is designed to supply either electricity or heat, in remote areas or ... -
European Research Program on Supercritical Water-Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2020)The article summarizes the major achievements and scope of the projects supported by the European Commission with the main focus on the supercritical water-cooled reactor, one of the concepts of the Generation IV reactors. ... -
Improvement of Steels' Corrosion Resistance in Liquid Lead and Lead-Bismuth by Coatings—Review
(The American Society of Mechanical Engineers (ASME), 2021)Heavy liquid metal (HLM) cooled systems are under wide investigation and development. The technology needs to study the materials corrosion, which has a different progress than corrosion caused by aqueous media. Improvement ... -
Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020
(The American Society of Mechanical Engineers (ASME), 2021)This special issue is dedicated primarily to research performed in the Research Centre Řež Centrum Výzkumu Řež (CVŘ hereafter) during the Research for SUSEN (R4S) project (project solved in CVŘ), which is the follow-up of ... -
Benefits, Drawbacks, and Future Trends of Brayton Helium Gas Turbine Cycles for Gas-Cooled Fast Reactor and Very-High Temperature Reactor Generation IV Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2020)Numerous studies are on-going on to understand the performance of generation IV (Gen IV) nuclear power plants (NPPs). The objective is to determine optimum operating conditions for efficiency and economic reasons in line ... -
Assessment of the External and Internal Exposure Risk Index and the Annual Gonadals Equivalent Dose Due to Cement in Côte D'Ivoire
(The American Society of Mechanical Engineers (ASME), 2020)Cement is the most used material in bulding activities in Côte d'Ivoire. Thus, most of the radiation exposure from the building materials is due to the cement. This work is part of radiation protection logic and therefore ... -
A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit
(The American Society of Mechanical Engineers (ASME), 2020)Due to the circulating nature of the fuel, there is a qualitative difference between xenon behavior in a molten salt reactor (MSR) compared to a solid fuel reactor. Therefore, the equations that describe 135Xe behavior in ... -
Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
(The American Society of Mechanical Engineers (ASME), 2020)The aim of the paper is to present the results of the investigation of the thermal conditions (temperature distribution, heat losses) in the support system of the vapor suppression tank (VST) of the vacuum vessel pressure ... -
Estimation of Radiological Consequences at a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code
(The American Society of Mechanical Engineers (ASME), 2020)Atmospheric dispersion modeling and radiation dose calculation have been performed for a generic 1000 MW water-water energy reactor (VVER-1000) assuming a hypothetical loss of coolant accident (LOCA). Atmospheric dispersion ... -
Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities
(The American Society of Mechanical Engineers (ASME), 2020)The article presents the analysis of the data on radionuclide composition of airborne discharges of 52 European nuclear power plants (NPPs) with water–water energetic reactor facilities (WWER), pressurized water reactor ... -
Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
(The American Society of Mechanical Engineers (ASME), 2020)Design against buckling of thin shells at high temperatures often follows the code RCC-MR. RCC-MR allows three methods to quantify shell imperfections for use in safe load calculations, where lower imperfection values raise ... -
Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
(The American Society of Mechanical Engineers (ASME), 2020)Melting of the terminal debris bed at the bottom of a Canada deuterium uranium (CANDU) 6 calandria vessel during a severe accident is studied using a three-dimensional transient finite element analysis. Settling of the ... -
Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe
(The American Society of Mechanical Engineers (ASME), 2020)Retention of molten corium inside calandria vessel is crucial for arresting accident progression in pressurized heavy water reactors (PHWRs) during severe accidents. Our earlier tests have demonstrated corium retention and ... -
Study on Description of Plant Status at Fukushima Accident by Emergency Action Level
(The American Society of Mechanical Engineers (ASME), 2020)This paper aims at verifying the current Japanese Emergency Response Guideline, especially the “notification” (reporting) scheme of emergency action level (EAL), through the analysis of the progress of Fukushima nuclear ... -
Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
(The American Society of Mechanical Engineers (ASME), 2020)By taking into account the ballistic mixing caused by recoil implantation and cascade collision, a model that describing effective free energy for alloys under irradiation from the perspective of diffusion equilibrium was ...