Browsing Journal of Nuclear Engineering and Radiation Science by Issue Date
Now showing items 1-20 of 891
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Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
(The American Society of Mechanical Engineers (ASME), 12/14/2022)Feedback reactivity caused by core deformation is one of the inherent safety features in a sodium-cooled fast reactor (SFR). To validate the evaluation models of the reactivity feedback equipped in the in-house plant ... -
Greetings from the Chair of the JSME Power Energy Systems Division
(The American Society of Mechanical Engineers (ASME), 12/2/2022 )Hitoshi AsanoI would like to take this opportunity to say New Year's greetings to the readers, reviewers, and editors of ASME Journal of Nuclear Engineering and Radiation Science as a Chair of the Power and Energy Systems ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 12/2/2022 )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), 12/2/2022 )Professor Igor L. Pioro, Editor-in-ChiefThe ASME Journal of Nuclear Engineering and Radiation Science (NERS)1 celebrates its eighth year (our first issue was published in January of 2015). On this occasion, I would like ... -
On Eight Years of the NERS and Vision of the Nuclear Engineering Division
(The American Society of Mechanical Engineers (ASME), 12/2/2022 )Jovica RiznicIt is with immense pleasure to write this column and join all of you, the Journal of Nuclear Engineering and Radiation Science (NERS) readers and contributors, in celebrating the journal’s eighth birthday. As ... -
Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity Factors
(The American Society of Mechanical Engineers (ASME), 2/22/2023 )Neutronics calculations are the basis of reactor analysis and design. Finite element methods (FEM) have gained increasing attention in solving neutron transport problems for the rigorous mathematical formulation and the ... -
Theoretical Investigation of the Gamma and Neutron Interaction Parameters of Some Inorganic Scintillators Using Phy-X/PSD and NGCal Software
(The American Society of Mechanical Engineers (ASME), 2/22/2023 )Inorganic scintillators are used in extreme environments and are essential in applications such as nuclear fission and fusion, radiation therapy, marine, and space exploration, etc. Radiation resistance is required for ... -
Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code Batan-FUEL
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)This paper presents the generation and the verification of the few-group homogenized cross section for Batan-FUEL code. This code is routinely used for fuel management in the G. A. Siwabessy Multipurpose Reactor (RSG-GAS). ... -
Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)The development of an accident tolerant nuclear fuel for water-cooled reactors would redefined the status of these reactors from traditional active safety to passive safety systems. As a possible solution toward enhancing ... -
Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With 252Cf Source in Center
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)Copper is an important material for the nuclear industry; therefore, the correct copper cross section are essential. This paper deals with benchmarking the fast neutron leakage spectrum from a copper block with an intense ... -
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 ... -
Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)In the design study of an advanced sodium-cooled fast reactor (advanced-SFR) in Japan Atomic Energy Agency (JAEA), the use of a specific fuel assembly (FA) with an inner duct structure called fuel assembly with an inner ... -
Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor Application
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)The growing terrorism threat based on the use of special nuclear materials (SNMs), which includes highly enriched uranium (HEU), weapons-grade plutonium (WGPu), or high-activity radiological sources has reinforced the need ... -
Machine Learning Metamodel of a Computationally Intense LOCA Code
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)The nuclear power industry is increasingly identifying applications of machine learning to reduce design, engineering, manufacturing, and operational costs. In some cases, applications have been deployed and are providing ... -
Long-Term Performance of Semimetallic Gaskets
(The American Society of Mechanical Engineers (ASME), 2/8/2023 1)Flexible graphite-based gaskets are used extensively in high-temperature applications as a replacement for asbestos-based gaskets. The effects of aging and temperature exposure on flexible graphite sheet gaskets were the ... -
Professor Geoffrey Hewitt on His 80th Birthday
(The American Society of Mechanical Engineers (ASME), 2015)Professor Geoffrey Hewitt is one of the wellknown names in the field of heat transfer, twophase flow, and nuclear engineering and is well respected among his colleagues in the heattransfer and nuclearengineering community ... -
Nuclear Power as a Basis for Future Electricity Generation
(The American Society of Mechanical Engineers (ASME), 2015)It is well known that electrical power generation is the key factor for advances in industry, agriculture, technology, and standards of living. Also, a strong power industry with diverse energy sources is very important ... -
Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant
(The American Society of Mechanical Engineers (ASME), 2015)The structural integrity of the containment vessel (CV) for a pressurized water reactor (PWR) plant under a lossofcoolant accident is evaluated by a safety analysis code that uses the average temperature of gas phase in ... -
Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test Reactor
(The American Society of Mechanical Engineers (ASME), 2015)The fluoridesaltcooled hightemperature reactor (FHR) is an advanced reactor concept that uses tristructural isotropic (TRISO) hightemperature fuel and lowpressure liquid salt coolant. A 20MWth test reactor, as the key step ... -
Application of the System Based Code Concept to the Determination of In Service Inspection Requirements
(The American Society of Mechanical Engineers (ASME), 2015)A new process for determination of inservice inspection (ISI) requirements was proposed on the basis of the system based code concept to realize effective and rational ISI by properly taking into account plantspecific ...