Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 61-80 of 891
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Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
(The American Society of Mechanical Engineers (ASME), 2023)The molten salt reactor (MSR) concept is among the Generation IV designs considered feasible for providing clean, safe, sustainable, and economical energy supplies to the world's population. The depletion of fuel for a ... -
Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
(The American Society of Mechanical Engineers (ASME), 2023)Advanced small modular reactors strive to improve reactor safety through increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes ... -
A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
(The American Society of Mechanical Engineers (ASME), 2023)Within an energy system where nuclear reactors will likely play a critical role, it is fundamental to have access to accurate and reliable computational tools that can predict the plants' behavior under different operating ... -
Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
(The American Society of Mechanical Engineers (ASME), 2023)The heavy water reactor concept Teplator is a pressure channel type reactor with independent systems for the primary coolant and the moderator. The present study analyses the low-pressure moderator cooling system of Teplator ... -
Influence of Noncondensable Gas–Dust Mixture on Direct Contact Condensation of Steam at Atmospheric Pressure
(The American Society of Mechanical Engineers (ASME), 2023)At the Department of Civil and Industrial Engineering (DICI) of the University of Pisa, an experimental research program, funded by International Thermonuclear Experimental Reactor (ITER) Organization, concerning steam ... -
Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
(The American Society of Mechanical Engineers (ASME), 2023)Passive containment filtered vent (PCFV) was installed in Nuclear Power Plant Krsko (NEK) in 2013 as part of the safety upgrade program. It is intended for severe accident consequences prevention and mitigation by ensuring ... -
Special Experimental Environment for Generation IV Reactors With Graphite Reflector
(The American Society of Mechanical Engineers (ASME), 2023)Nowadays, there is an increasing demand for new small modular reactors (SMR) reactors with a wide range of applications, often classified as a new Generation-IV reactors. Unfortunately, there is no commercially operating ... -
Total Loss of Feedwater Analysis of Pressurized Water Reactor Using RELAP5
(The American Society of Mechanical Engineers (ASME), 2023)In Europe, the design extension conditions (DEC) were introduced after the Fukushima Dai-ichi accident as preferred method for giving due consideration to the complex sequences and severe accidents without including them ... -
Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
(The American Society of Mechanical Engineers (ASME), 2023)Uncertainty and sensitivity methods are increasingly used in safety analyzes of nuclear power plants to address the unreliability of input data, numerical models, and, in general, the lack of knowledge regarding certain ... -
Greetings From the Chair of the JSME Power Energy Systems Division
(The American Society of Mechanical Engineers (ASME), 2023)Takashi KigaI would like to extend New Year's greetings to the readers, reviewers, and editors of the ASME Journal of Nuclear Engineering and Radiation Science (NERS) as Chair of the Power and Energy Systems Division (PESD) ... -
NED Chair's Message
(The American Society of Mechanical Engineers (ASME), 2023)Dr. Asif Arastu ASME/NED ChairAt the ninth anniversary of the first issue of Journal of Nuclear Engineering and Radiation Science (JNERS), it is my great pleasure to thank and recognize all the individuals who have contributed ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 2023)The Reviewers of the Year Award is given to reviewers who have made an outstanding contribution to the journal in terms of the quantity, quality, and turnaround time of reviews completed during the past 12 months. The prize ... -
Editorial
(The American Society of Mechanical Engineers (ASME), 2023)Professor Igor L. Pioro, Editor-in-ChiefThe ASME Journal of Nuclear Engineering and Radiation Science (NERS)1 celebrates its tenth year from the date of establishing (the Journal was established in 2014) and ninth year ... -
Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
(The American Society of Mechanical Engineers (ASME), 4/17/2023 )Additive manufacturing (AM) is a transformational digital manufacturing technology featured with rapidity, customizability, precision, and economy, which is fundamentally altering the way components are designed and ... -
Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
(The American Society of Mechanical Engineers (ASME), 5/31/2023 )This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the YH2 ... -
Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
(The American Society of Mechanical Engineers (ASME), 3/14/2023 )A new subassembly type passive reactor shutdown device is proposed to expand the diversity and robustness of core disruptive accident prevention measures for sodium-cooled fast reactors (SFRs). The device contains pins ... -
Main Parameters Influencing the Level of Labile Contamination and the Removal Factor
(The American Society of Mechanical Engineers (ASME), 5/31/2023 )Several nuclear facilities are currently being decommissioned in France, on CEA and EDF sites. The decommissioning process as a whole, with cutting operations and nuclear waste management presents workers with significant ... -
Handbook of Generation IV Nuclear Reactors Edition 2
(The American Society of Mechanical Engineers (ASME), 5/31/2023 )This second edition of the Handbook of Generation IV Nuclear Reactors1 combines the history of development, research, industrial-operating experience, advanced designs, systems, and safety analysis, and applications of ... -
Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)The isotope ratio method (IRM) is a technique used for estimating the energy production in a fission reactor by measuring isotope ratios in nonfuel reactor components. This method has been successfully demonstrated on the ... -
A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography
(The American Society of Mechanical Engineers (ASME), 3/13/2023 )X-ray radiography has proved to be essential in medical imaging and examination of material structures because it is noninvasive and generates images based on well-understood attenuation characteristics of materials. For ...