Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 781-800 of 913
-
Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition
(The American Society of Mechanical Engineers (ASME), 2017)The objective of current study is to develop and verify computer models to accurately predict the behavior of reactor structural components under operating and off-normal conditions. Indian pressurized heavy water reactors ... -
Collapse Criterion for the CANDU 6 Calandria Vault Floor During a Severe Accident
(The American Society of Mechanical Engineers (ASME), 2017)The thickness at which the calandria vault floor in a generic CANDU 6 nuclear reactor may collapse while undergoing molten core–concrete interaction (MCCI) was studied using an approximate analytical model and a finite-element ... -
Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
(The American Society of Mechanical Engineers (ASME), 2017)The International Atomic Energy Agency (IAEA) organized a coordinated research project (CRP) on “Benchmarking Severe Accident Computer Codes for Heavy Water Reactors (HWR) Applications,” (IAEA TECDOC Series No. 1727), and ... -
Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
(The American Society of Mechanical Engineers (ASME), 2017)The Nuclear Regulatory Commission (NRC) has considered revision of 10-CFR-50.46C rule (Borchard and Johnson, 2013, “10 CFR 50.46c Rulemaking: Request to Defer Draft Guidance and Extension Request for Final Rule and Final ... -
Statistical Modeling of Stratified Two-Phase Flow
(The American Society of Mechanical Engineers (ASME), 2017)A new numerical model for stratified two-phase flows with wavy interface is derived in this study. Assuming an equilibrium condition between turbulent kinetic energy, potential energy, and surface energy, the turbulent ... -
Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India
(The American Society of Mechanical Engineers (ASME), 2017)The technology of pressurized heavy water reactors (PHWRs) which was developed with prime objectives of using natural uranium fuel, implementing on power fuelling, utilizing mined uranium most effectively, and achieving ... -
Special Section: Pressurized Heavy Water Reactors Safety
(The American Society of Mechanical Engineers (ASME), 2017) -
Pressurized Heavy Water Reactor Technology: Its Relevance Today
(The American Society of Mechanical Engineers (ASME), 2017)The pressurized heavy water reactor (PHWR) technology was conceived in Canada and has moved to several nations for commercial production of electricity. Currently, 49 power reactors operate with PHWR technology producing ... -
Neutronic Design Features of a Transportable Fluoride Salt Cooled High Temperature Reactor
(The American Society of Mechanical Engineers (ASME), 2016)The fluoridesaltcooled hightemperature reactor (FHR) is a new reactor concept, which combines lowpressure liquid salt coolant and hightemperature tristructural isotropic (TRISO) particle fuel. The refractory TRISO particle ... -
European Project “Supercritical Water Reactor Fuel Qualification Testâ€: Summary of General Corrosion Tests
(The American Society of Mechanical Engineers (ASME), 2016)The main target of the EUROATOM FP7 project “Fuel Qualification Test for SCWR†is to make significant progress toward the design, analysis, and licensing of a fuel assembly cooled with supercritical water in a research ... -
Numerical Analysis on Heat Transfer Deterioration of Supercritical Fluid in the Vertical Upward Tubes
(The American Society of Mechanical Engineers (ASME), 2016)Heattransfer characteristics are especially significant among all issues for the supercritical watercooled reactors (SCWRs). The twopeak walltemperature phenomenon that could be verified by Shitsman and Jackson’s experiments ... -
A Study of Acoustic Wave Resonance in Water Filled Tubes With Different Wall Thicknesses and Materials
(The American Society of Mechanical Engineers (ASME), 2016)Acoustic resonance of a fluidfilled tube with closed and open outlet ends for zero and turbulent mean flows is investigated both experimentally and numerically for different wall materials and thicknesses. The main goal ... -
Performance of High Temperature Materials for Efficient Power Plants: The Waterside Challenge
(The American Society of Mechanical Engineers (ASME), 2016)Supercritical (SC) service at high operating values aims for good plant efficiency, but the waterside oxidation resistance can then become lifelimiting. In this paper, selected materials and modeling options are compared ... -
U233 Data Evaluation for Criticality Study
(The American Society of Mechanical Engineers (ASME), 2016)The aim of this study is to investigate the available U233 cross section data for adequate calculation of critical benchmark experiments, to calculate the multiplication factor Keff for several benchmarks in both fast and ... -
Analysis of Computational Fluid Dynamics Code FLUENT Capabilities for Supercritical Water Heat Transfer Applications in Vertical Bare Tubes
(The American Society of Mechanical Engineers (ASME), 2016)In this paper, the computational fluid dynamics (CFD) code FLUENT was used to predict walltemperature profiles inside vertical bare tubes with supercritical water (SCW) as the cooling medium, to assess the capabilities of ... -
Optimization of Moderator Design for Explosive Detection by Thermal Neutron Activation Using a Genetic Algorithm
(The American Society of Mechanical Engineers (ASME), 2016)An optimal design analysis is carried out for an explosives’ detection system (EDS) based on thermal neutron activation (TNA) of a sample under investigation. The objective of this work is to use a genetic algorithm (GA) ... -
An Experiment of Natural Circulation Flow and Heat Transfer With Supercritical Water in Parallel Channels
(The American Society of Mechanical Engineers (ASME), 2016)An experiment of natural circulation of supercritical water in parallel channels was performed in bare tubes of inner diameter 7.98آ mm and heated length 1.3آ m, covering the ranges of pressure of 24.7–25.5آ MPa, mass ... -
European Project “Supercritical Water Reactor–Fuel Qualification Testâ€: Results of Fuel Pin Mock up Tests
(The American Society of Mechanical Engineers (ASME), 2016)The main target of the EURATOM FP7 project “fuel qualification test for supercritical watercooled reactor†was to make significant progress toward the design, analysis, and licensing of a fuel assembly cooled with ... -
Experimental and Numerical Study of Supercritical Carbon Dioxide Flow Through Valves
(The American Society of Mechanical Engineers (ASME), 2016)The supercritical carbon dioxide (sCO2) Brayton cycle shows advantages such as high efficiency, compactness, and low capital cost. These benefits make it a competitive candidate for futuregeneration powerconversion cycles. ... -
On Some Relevant Effects in the Simulation of Flow Stability With Fluids at Supercritical Pressure
(The American Society of Mechanical Engineers (ASME), 2016)The paper collects and discusses findings emerging from the analysis of systems operating with fluids at supercritical pressure, with reference to flow stability. In particular, the influence of heating structures and ...