Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 81-100 of 891
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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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
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 ... -
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
(The American Society of Mechanical Engineers (ASME), 3/13/2023 )The objective of this paper is to quantify the coupling effect on the power distribution of sodium-cooled fast reactors (SFRs), specifically the European SFR. Calculations are performed with several state-of-the-art reactor ... -
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 ... -
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 ... -
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 ... -
Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in SodiumCooled Fast Reactors
(The American Society of Mechanical Engineers (ASME), 2022)Feedback reactivity caused by core deformation is one of the inherent safety features in a sodiumcooled fast reactor (SFR). To validate the evaluation models of the reactivity feedback equipped in the inhouse plant dynamics ... -
Greetings from the Chair of the JSME Power Energy Systems Division
(The American Society of Mechanical Engineers (ASME), 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 ... -
On Eight Years of the NERS and Vision of the Nuclear Engineering Division
(The American Society of Mechanical Engineers (ASME), 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 ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 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), 2022)Professor Igor L. Pioro, EditorinChiefThe 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 to ...