Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 581-600 of 913
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Numerical Simulation of Supercritical Carbon Dioxide Critical Flow in the Nozzle Tube
(The American Society of Mechanical Engineers (ASME), 2018)The supercritical carbon dioxide (S-CO2) Brayton gas turbine cycle has been studied as an efficient and cost-effective option for advanced power systems. One major safety issue for any power cycle is a pipe break and the ... -
Fuel Assembly Concept of the Canadian Supercritical Water-Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2018)The Canadian supercritical water-cooled nuclear reactor (SCWR) is a 2540 MWth channel-type SCWR concept that employs 336 fuel channels in the reactor core. Each fuel channel includes a pressure tube that is submerged in a ... -
Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
(The American Society of Mechanical Engineers (ASME), 2018)Due to the advantages of small volume, light weight, and long-time running, nuclear reactor can provide an ideal energy source for space crafts. In this paper, two small compact prismatic nuclear reactors with different ... -
Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model
(The American Society of Mechanical Engineers (ASME), 2018)This study investigates the reactor core physical properties of the AP1000®, which applies the MCNP4a program to model the AP1000 reactor core with the parameters and data from the design control document (DCD, Rev. 19) ... -
Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2018)The effective thermal diffusivity and conductivity of pebble bed in the high temperature gas-cooled reactor (HTGR) are two vital parameters to determine the operating temperature and power in varisized reactors with the ... -
Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP
(The American Society of Mechanical Engineers (ASME), 2018) -
Risk Analysis of Spent Fuel Pool Caused by Seismic Events
(The American Society of Mechanical Engineers (ASME), 2018)Spent fuel pool (SFP) stores fuel assemblies removed from the reactor over the years. SFP and its accident mitigation measures may fail simultaneously at the time of the earthquake, which may cause serious accident ... -
Investigations of Rod Positions for Treat M8CAL Analyses
(The American Society of Mechanical Engineers (ASME), 2018)The transient reactor test facility (TREAT), a graphite moderated experimental reactor, is scheduled to restart in late 2017. There is now renewed interest in development of capabilities to model and simulate the TREAT ... -
Study on Optimization Design for CSR1000 Core
(The American Society of Mechanical Engineers (ASME), 2018)An optimization design of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWe (CSR1000) conceptual core is proposed. Steady-state performance of the proposed core is then studied with ... -
Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
(The American Society of Mechanical Engineers (ASME), 2018)Accident tolerant fuels (ATF) and steam generator (SG) auxiliary feedwater (AFW) extended operation are two important methods to increase the coping time for nuclear power plant safety response. In light of recent efforts ... -
Characteristics of Thermal–Hydraulic and Heat Transfer in Liquid Windowless Target of Accelerator Driven Subcritical
(The American Society of Mechanical Engineers (ASME), 2018)In recent years, the morphological characteristics and stabilization methods of free interface in liquid windowless target become hot research topics in accelerator driven subcritical system (ADS). Based on the structure ... -
ASME/NED Chair's Message
(The American Society of Mechanical Engineers (ASME), 2018)ASME/NED Chair's Message;tulations! As a high quality hard copy of the October 2017 issue has been published, the third year of operation has been very successfully completed for the Journal of Nuclear Engineering and ... -
Effect of Structural State and Surface Finishing on Corrosion Behavior of 1.4970 Austenitic Steel at 400 and 500 °C in Flowing Pb-Bi Eutectic With Dissolved Oxygen
(The American Society of Mechanical Engineers (ASME), 2018)The effect of structural state (solution annealed (SA) and after 40% cold work (CW)) and surface finishing (turning, grinding, and polishing) on the corrosion behavior of austenitic 1.4970 (15-15 Ti) steel in flowing (2 ... -
Irradiation Issues and Material Selection for Canadian SCWR Components
(The American Society of Mechanical Engineers (ASME), 2018)The Canadian super critical water-cooled reactor (SCWR) concept requires materials to operate at higher temperatures than current generation III water-cooled reactors. Materials performance after radiation damage is an ... -
Development, Distribution, and Maintenance of Application Security Controls for Nuclear
(The American Society of Mechanical Engineers (ASME), 2018)The generic concept of security controls, as initially deployed in the information security domain, is gradually used in other business domains, including industrial security for critical infrastructure and cybersecurity ... -
Characterization of Alloy 214 After Exposure to Superheated Steam at 800 °C
(The American Society of Mechanical Engineers (ASME), 2018)In this study, an Al-containing alloy 214 was evaluated in superheated steam at 800 °C for a duration of 600 h. The purpose of using superheated steam was to simulate the supercritical water (SCW) condition at higher ... -
Numerical Simulation Research on the Performance of SCWR Fuel Rod
(The American Society of Mechanical Engineers (ASME), 2018)Because of the high temperature and high pressure characteristics of supercritical water-cooled reactor (SCWR), the thermal hydraulic performance of SCWR is greatly different from pressurized water reactor (PWR), which ... -
A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor
(The American Society of Mechanical Engineers (ASME), 2018)A fast breeder reactor (FBR) is considered as the promising technology in terms of load reduction on the environment, because the FBR has capability to improve usage efficiency of uranium resources and can reduce high-level ... -
Analysis Method for Impact and Dispersion Behavior of Water-Filled Tank
(The American Society of Mechanical Engineers (ASME), 2018)A new Japanese nuclear regulation involves estimating the possible damage to plant structures due to intentional aircraft impact. The effect of aircraft impact needs to be considered in the existing nuclear power plants. ... -
Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models
(The American Society of Mechanical Engineers (ASME), 2018)The paper presents the computational fluid dynamics (CFD) combustion modeling approach based on two combustion models. This modeling approach was applied to a hydrogen deflagration experiment conducted in a large-scale ...