Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 121-140 of 891
-
Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU
(The American Society of Mechanical Engineers (ASME), 2022)In many jurisdictions, filtered containment venting systems are an integral part of severe accident management guidelines but are normally only used as a last resort, to be manually activated when the containment pressure ... -
Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2022)Lattice physics calculations have been carried out to evaluate the performance and safety characteristics of a modified high temperature gas-cooled reactor (HTGR) prismatic fuel block concept, based on the MHTGR-350 benchmark ... -
Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors
(The American Society of Mechanical Engineers (ASME), 2022)Axial power peaking is a phenomenon with safety implications for pressure tube heavy water reactors (PT-HWRs). Since PT-HWRs use shorter (∼50 cm) bundles, there are small axial gaps, which expose the ends of the fuel ... -
Comparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes
(The American Society of Mechanical Engineers (ASME), 2022)A new design of a small power accelerator-driven system (ADS) using inert matrix fuel—ceramic–ceramic matrix (CERCER) and ceramic-metallic matrix (CERMET) was proposed in our previous work for high transmutation rate, small ... -
Neutronic Evaluation of Light Water Reactor-Based Small Modular Reactor With Transuranic Fuel and Comparison With Different Core Configuration of UO2 and Mixed Oxide Fuel
(The American Society of Mechanical Engineers (ASME), 2022)Neutronic and burnup assessment of a light water reactor (LWR)-based small modular reactor (SMR) core with transuranic fuel (TRU) was carried out and compared with UO2 fuel and mixed oxide fuel (MOX) for different core ... -
Experimental Evaluation of Two-Phase Heat Transfer Coefficient Under Oscillatory Flow Conditions and Correlation Development
(The American Society of Mechanical Engineers (ASME), 2022)Natural circulation boiling water reactors (NCBWRs) are prone to flow instabilities. Due to instabilities, heat transfer deteriorates. However, the extent to which the heat transfer coefficient (HTC) deteriorates is not ... -
Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels
(The American Society of Mechanical Engineers (ASME), 2022)Pressure loss coefficients are generally required by subchannel and system thermalhydraulics codes. These coefficients are not readily available for small modular reactors (SMRs) featuring nonconventional designs and novel ... -
Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate
(The American Society of Mechanical Engineers (ASME), 2022)Wall functions are generally used in a turbulent analysis with a computational fluid dynamics (CFD) code and large computation cells. The logarithmic law based on the analogy between momentum, energy, and mass transfer is ... -
Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection
(The American Society of Mechanical Engineers (ASME), 2022)Severe accidents of light water reactors with core degradation can lead to the formation of a, so-called, debris bed inside the reactor cavity. In the scenario of depleted residual water, the bed can partially melt and ... -
The Heat Capacity of PuO2 at High Temperature: Molecular Dynamics Calculations
(The American Society of Mechanical Engineers (ASME), 2022)A new generation of fast breeder reactors (FBRs) is under development with the objective of making nuclear energy more sustainable. Most promising reactor designs are loaded, at least during their early phase of deployment, ... -
Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows
(The American Society of Mechanical Engineers (ASME), 2022)An analytical expression for turbulent kinematic viscosity (νt), based solely on the hydraulic Reynolds number (Re), was derived and evaluated. The analytical expression is valid for the fast estimation of νt for internal, ... -
Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
(The American Society of Mechanical Engineers (ASME), 2022)Most of today's operating nuclear plants that were originally designed for 30 or 40-year life are facing the long-term operation issues. Therefore, it is of meaningful importance to assess the time-dependent degradation ... -
Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II
(The American Society of Mechanical Engineers (ASME), 2022)The general context of this paper is an evaluation of strategies that can be used to mitigate aerosol dispersion during fuel debris or corium retrieval in damaged Fukushima Daiichi reactors. Knowledge of the aerosol source ... -
Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels
(The American Society of Mechanical Engineers (ASME), 2022)Thermalhydraulic analyses using subchannel codes (e.g., ASSERT-PV) are performed as a support tool to evaluate safety margins and the key parameters. Advanced fuels have recently attracted the international community's ... -
Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
(The American Society of Mechanical Engineers (ASME), 2022)This paper deals with a general methodology to evaluate the Source Term (ST) and the Radiological Consequences (RC) of a hypothetical Severe Accident (SA) at a Fukushima-like Spent Fuel Pool (SFP) by coupling ASTEC 2.1 and ... -
Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector
(The American Society of Mechanical Engineers (ASME), 2022)An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessary to monitor the neutron flux and control the chain reaction, therefore, the ex-core neutron flux measurement is one of ... -
Suggestion on Improving Small Branch BOSS Joints Welding Quality
(The American Society of Mechanical Engineers (ASME), 2022)Due to the structural constraints, mandatory volumetric examination is not implemented on small branch BOSS joints of nuclear power plant, which leads to internal defects cannot be detected thoroughly, causing potential ... -
Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping
(The American Society of Mechanical Engineers (ASME), 2022)Neutron transmutation doping (NTD) is one of the several techniques used for n-type doping with good homogeneity. NTD performances were investigated in this work within a project funded by the Academy of Scientific Research ... -
Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER
(The American Society of Mechanical Engineers (ASME), 2022)Dust resuspension inside the vacuum vessel (VV) is one of the safety issues of the fusion reactor ITER. Plasma interaction with the plasma facing components (PFC) leads to their erosion, generating dust. One of the accident ... -
Estimating Radon Excess Lung Cancer at the Babylon Cement Plant in Iraq
(The American Society of Mechanical Engineers (ASME), 2022)In this work, radon excess lung cancer (ELC) was estimated for 14 soil samples from the Babylon cement plant in Iraq. A CR-39 nuclear track detector was used to measure uranium and radon (222Rn) concentrations in the soil ...