Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 801-820 of 913
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Design and Implementation of an Automated Gamma Probe for Jet Boring Uranium Mining
(The American Society of Mechanical Engineers (ASME), 2016)A proofofconcept detector prototype capable of collecting and storing radiometric data in the jet boring system (JBS) during pilot hole drilling at the Cigar Lake uranium mine is presented. Cigar Lake is the world’s ... -
Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers
(The American Society of Mechanical Engineers (ASME), 2016)This paper presents a steadystate computational fluid dynamics approach to supercritical water flow and heat transfer in a rod bundle with grid spacers. The current model was developed using the ANSYS Workbench 15.0 software ... -
Effects of Decay Heat Distribution on Water Temperature in a Spent Fuel Pit and Prediction Errors With a One Region Model
(The American Society of Mechanical Engineers (ASME), 2016)A prediction system with a oneregion (1R) model was developed to predict water temperature in a spent fuel pit (SFP) after the shutdown of its cooling systems based on threedimensional (3D) thermalhydraulic behavior computed ... -
Analysis and Assessment of a Gas Turbine Modular Helium Reactor for Nuclear Desalination
(The American Society of Mechanical Engineers (ASME), 2016)A thermodynamic analysis of the coupling of a reverse osmosis (RO) process with the gas turbinemodular helium reactor (GTMHR) is presented in which the waste heat is utilized for the generation of steam as it is expanded ... -
COBRA TF Simulation of DNB Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments
(The American Society of Mechanical Engineers (ASME), 2016)COBRATF (Coolant Boiling in Rod Arrays–Two Fluid), or CTF, is a transient subchannel code selected to be the reactor core thermalhydraulic simulation tool in the multiphysics codedevelopment project of the Consortium for ... -
On Calculating Heat Transfer and Pressure Drop of Supercritical Pressure Coolants
(The American Society of Mechanical Engineers (ASME), 2016)Specific features of thermophysical properties of singlephase supercriticalpressure (SCP) coolants and typical ranges of their thermodynamic state that determine heattransfer regularities are presented. A brief analysis ... -
Direct Numerical Simulation of Heated Turbulent Pipe Flow at Supercritical Pressure
(The American Society of Mechanical Engineers (ASME), 2016)For fluids at supercritical pressure, the phase change from liquid to gas does not exist. Meanwhile, the fluid properties change drastically in a narrow temperature range. With supercritical fluid as working fluid in a ... -
HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity
(The American Society of Mechanical Engineers (ASME), 2016)The Japan Atomic Energy Agency (JAEA) initiated a hightemperature engineering test reactor (HTTR) demonstration program in accordance with recommendations of a task force established by the Ministry of Education, Culture, ... -
Global Neutron Calculations, by M. Makai, D. P. Kis, and J. Vegh. Bentham Science Publishers Ltd., UAE, 2015, 552 pp., eISBN 978 1 68108 027 7, ISBN978 1 68108 028 4.
(The American Society of Mechanical Engineers (ASME), 2016)Several excellent texts have been written on the subject of nuclear reactor theory and analysis. The material and orientation of “classical†treatments may be seen as somehow outdated for today’s methods and techniques ... -
Prediction Method of Countercurrent Flow Limitation in a Pressurizer Surge Line and Its Evaluation for a 1/10 Scale Model
(The American Society of Mechanical Engineers (ASME), 2016)The method for predicting countercurrent flow limitation (CCFL) and its uncertainty in an actual pressurizer surge line of a pressurized water reactor (PWR) using 1/10scale air–water experimental data, onedimensional ... -
An Experimental Study on Head Loss of Prototypical Fibrous Debris Beds During Loss of Coolant Accident Conditions
(The American Society of Mechanical Engineers (ASME), 2016)The United States Nuclear Regulatory Commission (NRC) initiated a generic safety issue (GSI191) assessing debris accumulation and resultant chemical effects on pressurized water reactor (PWR) sump performance. GSI191 has ... -
A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7 Rod Bundle
(The American Society of Mechanical Engineers (ASME), 2016)Heat transfer in supercritical water reactors (SCWRs) shows a complex behavior, especially when the temperatures of the water are near the pseudocritical value. For example, a significant deterioration of heat transfer may ... -
In Memoriam: Jan Kysela
(The American Society of Mechanical Engineers (ASME), 2016)Jan’s contribution to nuclear water chemistry, utilization of research reactors, and nuclear fusion research strongly impacted the technology development on both the national and international scientific scenes. Working ... -
List of Reviewers for 2015
(The American Society of Mechanical Engineers (ASME), 2016)Asif Arastu -
The Development of Candling Module Code in Module In vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large Break LOCA
(The American Society of Mechanical Engineers (ASME), 2016)The occurrence of Fukushima has increased the focus on the development of severe accident codes and their applications. As a part of Chinese “National Major Projects,†a module invessel degraded analysis code (MIDAC) ... -
Editorial
(The American Society of Mechanical Engineers (ASME), 2016)Guest Editors of the Special Section in 1(4), October 2015: Selected Papers from the 2014 ASME IMECE in Montreal: -
Overview on Fusion Nuclear Technology Experimental Testing
(The American Society of Mechanical Engineers (ASME), 2016)Research Centre Rez in the Czech Republic has carried out a number of research and development activities on the nuclear technology of the fusion reactor International Thermonuclear Experimental Reactor (ITER). These ... -
A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods
(The American Society of Mechanical Engineers (ASME), 2016)This work presents a reduced order model (ROM) aimed at simulating nuclear reactor control rods movement and featuring fastrunning prediction of reactivity and neutron flux distribution as well. In particular, the reduced ... -
Implicit Model Equation for Hydraulic Resistance and Heat Transfer including Wall Roughness
(The American Society of Mechanical Engineers (ASME), 2016)Heat transfer to water at supercritical pressure within the core of a supercritical water reactor must be predicted accurately to ensure safe design of the reactor and prevent overheating of the fuel cladding. In the ... -
List of Reviewers for 2014
(The American Society of Mechanical Engineers (ASME), 2016)Andrea Cioncolini