Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 401-420 of 913
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The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition
(The American Society of Mechanical Engineers (ASME), 2020)The lower head molten pool model is an important model for the in-vessel retention (IVR) effectiveness evaluation. It has the characteristics of complex relationship, many input parameters, and large uncertainty. The ... -
Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments
(The American Society of Mechanical Engineers (ASME), 2020)The Moody and Henry–Fauske critical flow models implemented in Advanced Process Simulation Software (apros) have been validated against Marviken critical flow experiments and compared with other available simulations of ... -
Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors
(The American Society of Mechanical Engineers (ASME), 2020)CATHENA has been successfully employed to simulate accident and startup transients in the development of the Canadian supercritical water reactor concept. This success is attributed to the implementation of a novel method ... -
Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
(The American Society of Mechanical Engineers (ASME), 2020)Canada is participating in the Generation IV (Gen IV) International Forum with a main focus on the pressure-tube-type supercritical water-cooled reactor (SCWR) concept. The subchannel code ASSERT-PV modified for SCWR ... -
Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
(The American Society of Mechanical Engineers (ASME), 2020)Canada is participating in the Generation IV International Forum with the main focus on the pressure-tube-type supercritical water-cooled reactor (SCWR) concept. The Canadian SCWR concept is a heavy-water moderated and ... -
A Critical Review of the Physics and Modeling of Deteriorated Heat Transfer in Supercritical Fluids
(The American Society of Mechanical Engineers (ASME), 2020)Modeling of deterioration of heat transfer (DHT) observed in fluid flows at supercritical pressure remains a challenge due to incomplete understanding of the underlying physics. Given the challenges involved in the ... -
A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating
(The American Society of Mechanical Engineers (ASME), 2020)This work is part of a benchmarking exercise organized by an IAEA in supercritical water-cooled reactor (SCWR) thermal-hydraulics aimed at improving the understanding and prediction accuracy of the thermal-hydraulic phenomena ... -
Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel
(The American Society of Mechanical Engineers (ASME), 2020)Fast neutron irradiation causes embrittlement of the reactor pressure vessel (RPV) material; therefore, it may end operation life before design lifetime. Well-known method to recuperate crystal lattice dislocations is ... -
Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C
(The American Society of Mechanical Engineers (ASME), 2020)In this study, three alumina-forming austenitic (AFA) steels (Fe-18Ni-12Cr-AlNbC, Fe-18Ni-12Cr-Al, and Fe-18Ni-16Cr-AlNbC) were exposed to superheated steam (SHS) at 700 °C for 1000 h to study their oxidation behavior. The ... -
About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept
(The American Society of Mechanical Engineers (ASME), 2020)Inherently poorer moderation in supercritical water-cooled reactors (SCWRs) due to average density lower than in light water reactors and the resulted spectral shift can be useful when we apply thorium fuel-cycle instead ... -
Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle
(The American Society of Mechanical Engineers (ASME), 2020)The application of relatively simple and cheap wrapped wire spacer in the European supercritical water-cooled reactor (SCWR) (high-performance light water reactor (HPLWR)) has been proposed in order to provide enhanced ... -
Research on Improved Simplified SCWR Assembly and Core Design
(The American Society of Mechanical Engineers (ASME), 2020)A new type of simplified assembly without “water rod” or solid moderator is identified to simplify China Supercritical Water-cooled Reactor with the rated electric power of 1000 MWel (CSR1000) core structure. A study on ... -
Numerical Simulation of a Steam Injector for Passive Residual Heat Removal
(The American Society of Mechanical Engineers (ASME), 2020)In the case of depressurization of a supercritical water-cooled reactor (SCWR), the steam pressure can be used to pump coolant back into the reactor, either by using a turbine driven pump or a steam injector. The latter ... -
Numerical Investigation on Heat Transfer of Supercritical Water With a Variable Turbulent Prandtl Number Model
(The American Society of Mechanical Engineers (ASME), 2020)Turbulent Prandtl number (Prt) has a great impact on the performance of turbulence models in predicting heat transfer of supercritical fluids. Unrealistic treatment of Prt may lead to large deviations of the prediction ... -
Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
(The American Society of Mechanical Engineers (ASME), 2020)The three-dimensional code system supercritical water-cooled reactor (SCWR) coupled neutronics/thermal-hydraulics analysis (SNTA) code is developed for SCWR core steady-state analysis by coupling neutronics/thermal-hydraulics ... -
General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C
(The American Society of Mechanical Engineers (ASME), 2020)The 300 MWel small Canadian supercritical water-cooled reactor (SCWR), which is a scaled-down version of the original 1200 MWel concept, has a smaller core, uses low enriched uranium fuel instead of a plutonium–thorium ... -
Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors?
(The American Society of Mechanical Engineers (ASME), 2020)The use of supercritical water (SCW) in GEN IV reactors is a logical approach to the ongoing development of nuclear energy. A proper understanding of the radiation chemistry and reactivities of transients in a reactor core ... -
Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2020)The Ninth International Symposium on Supercritical Water-Cooled Reactors (IS-SCWRs) was successfully held on Mar. 11–13, 2019 at the Vancouver Marriott Hotel, Vancouver, BC, Canada. It was hosted by the Canadian Nuclear ... -
Leakage Estimate in Nonuniformly Compressed Packing Rings
(The American Society of Mechanical Engineers (ASME), 2020)Characterizing the permeation performance of nanoporous material is an initial step toward predicting microflows and achieving acceptable designs in sealing and filtration applications. This study deals with analytical, ... -
Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
(The American Society of Mechanical Engineers (ASME), 2020)The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulant fuel material (ZrO2) that would contribute, not only to Fukushima Daiichi (1 F) decommissioning, but also ...