Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 221-240 of 913
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Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
(The American Society of Mechanical Engineers (ASME), 2021)A study is carried out on the build-up and characterization of ultraslow nuclear burn-up wave in epithermal neutron multiplying medium for slab geometry. Uranium-plutonium fissile medium is considered for the calculation. ... -
Hybrid Nodal Integral/Finite Element Method for Time-Dependent Convection Diffusion Equation
(The American Society of Mechanical Engineers (ASME), 2022)Nodal integral methods (NIM) are a class of efficient coarse mesh methods that use transverse averaging to reduce the governing partial differential equation(s) (PDE) into a set of ordinary differential equations (ODE). ... -
Investigation of Critical Heat Flux for Plutonium-Based Mixed Oxide Advanced Fuel Bundle Design
(The American Society of Mechanical Engineers (ASME), 2022)The critical heat flux (CHF) performance of an advanced plutonium-based mixed oxide (MOX) fuel for potential use in a pressure tube heavy water reactor (PT-HWR) has been studied experimentally at Canadian Nuclear Laboratories ... -
Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark
(The American Society of Mechanical Engineers (ASME), 2021)In best estimate plus uncertainty approach for thermal-hydraulic simulation in nuclear engineering, a crucial step for the qualification of the scenario simulation is the discretization, i.e., the nodalization of nuclear ... -
Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
(The American Society of Mechanical Engineers (ASME), 2021)Quenching is an important phenomenon when the emergency core cooling system is put into operation during loss of coolant accident (LOCA) in a nuclear reactor. In this study, an experimental apparatus is designed and ... -
Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube
(The American Society of Mechanical Engineers (ASME), 2021)Thermal efficiency and safety of generation-IV nuclear-power-reactor concept supercritical water-cooled reactor (SCWR) are largely dependent on the coupled supercritical water (SCW) thermophysical properties and heat ... -
Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
(The American Society of Mechanical Engineers (ASME), 2021)Two-phase flows including a phase change such as liquid–vapor flows play an important role in many industrial applications. A deeper understanding of the phase change phenomena is required to improve the performance and ... -
Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
(The American Society of Mechanical Engineers (ASME), 2021)Space fission power systems can enable ambitious solar-system and deep-space science missions. The heat pipe-cooled reactor is one of the most potential candidates for near-term space power supply, featuring safety, ... -
A Heuristic for Designing Hybrid Compact Heat Exchangers for Nuclear Applications
(The American Society of Mechanical Engineers (ASME), 2021)Hybrid compact heat exchangers (HCHEs) are a potential source of innovation for intermediate heat exchangers in nuclear industry, with HCHEs being designed for generation IV nuclear power applications. Compact heat exchangers ... -
Molecular Dynamics of Supercritical Water for Nuclear Data Development
(The American Society of Mechanical Engineers (ASME), 2021)The Canadian supercritical water-cooled reactor was selected as one of the Generation IV International Forum initiatives for reactor design. It uses supercritical light water as a coolant under operating conditions of ... -
In Memoriam: Professor Pavel Leonidovich Kirillov (Aug. 20, 1927–Oct. 10, 2021)
(The American Society of Mechanical Engineers (ASME), 2022)Professor Pavel Leonidovich KirillovProfessor Pavel L. Kirillov died on Oct. 8, 2021, on his 95th year after a life as a husband, father, and an internationally renowned scientist, researcher, and educator in the field of ... -
Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO2 Pool in Natural Convection
(The American Society of Mechanical Engineers (ASME), 2021)This work, performed within the European sodium fast reactor safety measures assessment and research tools (ESFR-SMART) H2020 European project, is part of a larger framework intending to reassess the modeling of heat ... -
Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
(The American Society of Mechanical Engineers (ASME), 2021)The experimental liquid metal loops hosted within the Karlsruhe Sodium laboratory (KASOLA) comprise a set of facilities to study liquid metal flows for various types of energy applications ranging from room temperature ... -
Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project
(The American Society of Mechanical Engineers (ASME), 2021)Based on feedback from existing reactors and current projects, the European sodium fast reactor-safety measures assessment and research tools (ESFR-SMART) project proposes an optimization of the secondary circuit with the ... -
ESFR-SMART Core Safety Measures and Their Preliminary Assessment
(The American Society of Mechanical Engineers (ASME), 2021)A large 3600 MW-thermal European sodium fast reactor (ESFR) concept has been studied in a European Horizon-2020 project since September 2017, following an earlier European project. In the paper, we describe new ESFR core ... -
Superphénix Benchmark Part II: Transient Results
(The American Society of Mechanical Engineers (ASME), 2021)The paper presents a transient simulation phase of the new benchmark on a large sodium fast reactor (SFR). This phase of the benchmark is devoted to the modeling of selected operational transients performed during startup ... -
Superphénix Benchmark Part I: Results of Static Neutronics
(The American Society of Mechanical Engineers (ASME), 2021)In the paper, the specification of a new neutronics benchmark for large sodium cooled fast reactor (SFR) core and results of modeling by different participants are presented. The neutronics benchmark describes the core of ... -
Decay Heat Characterization for the European Sodium Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2021)In this work, a detailed assessment of the decay heat power for the commercial-size European sodium-cooled fast reactor (ESFR) at the end of its equilibrium cycle has been performed. The summation method has been used to ... -
Severe Accidents in Sodium-Cooled Fast Reactors: Computational Fluid Dynamics Sensitivity Studies on the Thermal Ablation of Core Catcher
(The American Society of Mechanical Engineers (ASME), 2021)The present work aims at testing the computational fluid dynamics capabilities to simulate erosion of materials which interact with a corium mass. The main foreseen application is the design of external/internal core ... -
Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing
(The American Society of Mechanical Engineers (ASME), 2021)The Eddy current flowmeter sensor plays an important part in the instrumentation of the future sodium fast reactors, which will allow when located above the core to detect plugging (partial or total) of a subassembly and ...