Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 421-440 of 913
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Application of Wireless Technologies in a Nuclear Plant: Evaluation of Electromagnetic Propagation With Different Computational Techniques
(The American Society of Mechanical Engineers (ASME), 2020)The aim of this work is to present a preliminary investigation on the propagation of electromagnetic fields generated by wireless technologies inside a nuclear facility or power plant. First, a survey of currently proposed ... -
Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2020)The safety of cooling water intake in nuclear power plants (NPPs) has gradually become an important factor affecting the safety of NPPs. Marine flora and fauna outbreaks are one of the main types affecting the safety of ... -
Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
(The American Society of Mechanical Engineers (ASME), 2020)Nordic boiling water reactor (BWR) design employs ex-vessel debris coolability in a deep pool of water as a severe accident management (SAM) strategy. Depending on melt release conditions from the vessel and core–melt ... -
Current Status of Reactors Deployment and Small Modular Reactors Development in the World
(The American Society of Mechanical Engineers (ASME), 2020)Due to emerging climate change concerns coupled with increased global energy demand, eventually the world needs to move to low-carbon-emission electricity-generating sources—nonrenewables, such as nuclear power, and ... -
Special Section: Selected Papers from ICONE-27
(The American Society of Mechanical Engineers (ASME), 2020)Guest Editorial team:Because of the in-depth review process, which has ensured high-quality papers, and the important topics that are discussed, we hope that this Special Section of the ASME Journal of Nuclear Engineering ... -
Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2020)The effects of postulated accidents, including dynamic effects of pipe ruptures, must be analyzed for licensing of nuclear power plants (NPPs). Applicants and licensees of NPPs have struggled to address U.S. Nuclear ... -
Professor Jyeshtharaj Bhalchandra Joshi on His 70th Birthday
(The American Society of Mechanical Engineers (ASME), 2020)Professor Jyeshtharaj B. JoshiProfessor Jyeshtharaj B. Joshi is one of the well-known names in the fields of chemical and nuclear engineering. He was born on the May 28, 1949, in Masur, Satara, Maharashtra, India. He ... -
A Resonated and Synchrophased Three Beams Neutron Cancer Therapy Installation
(The American Society of Mechanical Engineers (ASME), 2020)The technique of composite region coupling by a neutron source at a common boundary of different regions that has been introduced in 2019 has allowed for an additive separation of variables neutron-density 3D wave analytical ... -
Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems
(The American Society of Mechanical Engineers (ASME), 2020)Individual systems or groups of systems related to the safety and operational instrumentation & control (I&C), and electrical systems are gradually replaced in existing nuclear power plants (NPPs) as part of ... -
Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method
(The American Society of Mechanical Engineers (ASME), 2020)Quantification of common cause failure (CCF) parameters and their application in multi-unit PSA are important to the safety and operation of nuclear power plants (NPPs) on the same site. CCF quantification mainly involves ... -
Mitigation of End-Flux-Peaking in Fresh CANDU Fuel Bundles Using Neutron Absorbers
(The American Society of Mechanical Engineers (ASME), 2020)End-flux-peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles, leading to an increase in fission rate and therefore greater heat generation. It is known that the ... -
Determination of βeff for ININ's TRIGA Reactor
(The American Society of Mechanical Engineers (ASME), 2020)The value of βeff for Training Research Isotopes of General Atomics (TRIGA) Mark III reactor, belonging to the National Institute of Nuclear Researches (ININ), is reported. The TRIGA Mark III reactor core was simulated ... -
Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”
(The American Society of Mechanical Engineers (ASME), 2020)This paper presents the analysis of reactivity initiated transients in an idealized, light water research reactor as a part of International Atomic Energy Agency (IAEA) safety related benchmark. The simulation model is ... -
The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors
(The American Society of Mechanical Engineers (ASME), 2020)Within emerging best-estimate-plus-uncertainty (BEPU) approaches, code output uncertainties can be inferred from the propagation of fundamental or microscopic uncertainties. This paper examines the propagation of fundamental ... -
Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor
(The American Society of Mechanical Engineers (ASME), 2020)The very-small, long-life, modular (VSLLIM) nuclear reactor generates 1.0–10 MWth, for ∼92 and 5.8 full power years (FPY), respectively, without refueling. This factory fabricated, assembled, and sealed reactor is cooled ... -
Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs
(The American Society of Mechanical Engineers (ASME), 2020)Retention of corium inside the calandria vessel (CV) by externally cooling it by calandria vault water is essential to mitigate severe accidents in pressurized heavy water reactor (PHWR). The thermal failure of CV can be ... -
Promising Neutron Irradiation Applications at the High Temperature Engineering Test Reactor
(The American Society of Mechanical Engineers (ASME), 2020)The high temperature gas-cooled reactor (HTGR) has advantages for irradiation applications such as large space available for irradiation at reflector region and high thermal neutron spectrum with the graphite moderator. ... -
Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
(The American Society of Mechanical Engineers (ASME), 2020)The constructive solid geometry (CSG) method is widely used in the Monte Carlo community because of its geometry flexibility. As the requirements of designing new reactors and development of deterministic methods, the CSG ... -
Exploring Synergy Among New Generation Technologies—Small Modular Reactor, Energy Storage, and Distributed Generation: A Strong Case for Remote Communities
(The American Society of Mechanical Engineers (ASME), 2020)With a steady rise in power demand in the remote communities in Canada, utilities are looking for new options to provide a reliable supply of electricity. While distributed generation is a promising option, scaling and ... -
Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors
(The American Society of Mechanical Engineers (ASME), 2020)The Pohang University of Science and Technology facility (POSTECH) experiments to mimic the siphon breaker system (SBS) of an open-type nuclear research reactor were simulated by computational fluid dynamics (CFD). Two ...