Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 361-380 of 913
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The Autoignition of Nuclear Reactor Power Plant Explosions
(The American Society of Mechanical Engineers (ASME), 2020)Explosive research proves that there is a common cause for most explosions in nuclear reactor power plants during normal operations and accident conditions. The autoignition of flammable hydrogen is a common cause for ... -
Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
(The American Society of Mechanical Engineers (ASME), 2020)Many factors need to be investigated before alternative nuclear fuel can be adapted for service in the harsh environment of a nuclear reactor. Urania, used conventionally as a nuclear fuel, has a low thermal conductivity, ... -
Application of a Graded Approach to Support the National Research Universal Reactor U-2 Experimental Loop Return to Service
(The American Society of Mechanical Engineers (ASME), 2020)The National Research Universal (NRU) reactor at Canadian Nuclear Laboratories (CNL) operated safely for over 60 years and supported a wide range of applications including, testing of fuels and materials under typical power ... -
Application of Stiffness Confinement Method in Transient Transport Calculation
(The American Society of Mechanical Engineers (ASME), 2020)Stiffness confinement method (SCM) can effectively alleviate the stiffness in the neutron kinetics equation and can use larger time steps to obtain the same calculation accuracy and improve the computational efficiency. ... -
A Study of Superhomogenization Applied to PHWR Lattices
(The American Society of Mechanical Engineers (ASME), 2020)To reduce computational expenses, full-core production-type neutronics calculations are customarily performed using a simplified core-model whereby large regions of the core, called nodes, are assumed to be homogeneous. ... -
Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow
(The American Society of Mechanical Engineers (ASME), 2020)In a reactor core meltdown under postulated severe accidents, the molten material called corium could be ejected or relocated through existing vessel penetrations. There exists, however, a potential for plugging of melt ... -
A Review of Molten Salt Reactor Xenon Analysis Literature
(The American Society of Mechanical Engineers (ASME), 2020)This paper presents a review of xenon analyses literature related to molten salt reactors (MSRs). A brief primer of reactor xenon theory is presented for fluid fueled reactors. A review of xenon analysis literature is ... -
Computational Fluid Dynamics Modeling of Fire and Human Evacuation for Nuclear Applications
(The American Society of Mechanical Engineers (ASME), 2020)The nuclear industry has seen an increased use of computational fluid dynamics (CFD) technology as a high-fidelity tool for design-basis and beyond-design-basis accident simulations. Among its applications, CFD modeling ... -
Fueling Machine Model for Simulation of Spent Fuel Behavior in Postulated Fuel Handling Accidents
(The American Society of Mechanical Engineers (ASME), 2020)On-power fueling is an important feature of the CANDU® reactor. Fueling is a routine operation with a large number of channel fueling visits made each year with the fueling machines acting as the key system. Hence, safety ... -
Editorial
(The American Society of Mechanical Engineers (ASME), 2020)Professor Igor L. Pioro, EditorThe ASME Journal of Nuclear Engineering and Radiation Science (NERS) celebrates its fifth year (our first issue was published in January 2015). On this occasion, I would like to congratulate ... -
Special Section: CNS's 8th International Conference on Simulation Methods in Nuclear Science and Engineering
(The American Society of Mechanical Engineers (ASME), 2020)Adriaan Buijs, Conference ChairThe eighth edition of the International Conference on Simulation Methods in Nuclear Science and Engineering was organized by the Canadian Nuclear Society and held in Ottawa, ON, Canada in ... -
Estimation of Flow-Accelerated Corrosion Rate in Nuclear Piping System
(The American Society of Mechanical Engineers (ASME), 2020)Flow-accelerated corrosion (FAC) is a life-limiting factor for the piping network of the primary heat transport system (PHTS) in CANDU® reactors. The pipe wall thinning caused by FAC is monitored by carrying out periodic ... -
Multiscale Mesoscale Modeling of Porosity Evolution in Oxide Fuels
(The American Society of Mechanical Engineers (ASME), 2020)The behavior of fission gas, notably accommodation within intra- and intergranular bubbles, influences the macroscopic properties and overall performance of oxide fuels. This work discusses progress to capture key fission ... -
ASME-NED Chair's Message
(The American Society of Mechanical Engineers (ASME), 2020)Dr. Shripad T. RevankarWith its successful publication since 2015, the Journal of Nuclear Engineering and Radiation Science founded by the Nuclear Engineering Division (NED) of the American Society of Mechanical Engineers ... -
Experimental Investigation on Flash Evaporation Related to Pipe Leakage
(The American Society of Mechanical Engineers (ASME), 2020)Pipelines such as the surge line and main pipe are easily subjected to thermal stratification and thermal fatigue as a result of the nonuniform temperature distribution in the nuclear power plants. When the surge line or ... -
High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor
(The American Society of Mechanical Engineers (ASME), 2020)A method to monitor the mechanical behavior and identify crack location and growth in a concrete structure element using a distributed fiber optic sensor (FOS) system is demonstrated experimentally by testing concrete ... -
Reviewer's Recognition
(The American Society of Mechanical Engineers (ASME), 2020)The Reviewers of the Year Award is given to reviewers who have made an outstanding contribution to the journal in terms of the quantity, quality, and turnaround time of reviews completed during the past 12 months. The prize ... -
Greetings From JSME and the Report on ICONE27
(The American Society of Mechanical Engineers (ASME), 2020)I would like to say New Year's greetings to all the readers of the Journal of Nuclear Engineering and Radiation Science.Before the Great East Japan Earthquake on March 11, 2011, 54 nuclear power plants were used in Japan ... -
Professor Masahiro Kawaji on His 65th Birthday
(The American Society of Mechanical Engineers (ASME), 2020)Professor Masahiro KawajiProfessor Masahiro Kawaji is one of the well-known names in the field of nuclear engineering and two-phase flow. He was born on Sept. 6, 1954 in Kagoshima, Japan. He received his B.A.Sc. in 1978 ... -
Application of Cross Sections Uncertainty Propagation Framework to Light and Heavy Water Reactor Systems
(The American Society of Mechanical Engineers (ASME), 2020)Uncertainty quantification has been recognized by the community as an essential component of best-estimate reactor analysis simulation because it provides a measure by which the credibility of the simulation can be assessed. ...