Nuclear Engineering and Design
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#1Xue Yang (Texas A&M University–Kingsville)
#1Xue Yang (Texas A&M University–Kingsville)
Abstract null null This research extends MATLAB PDE Toolbox to model nuclear reactors by solving the 2-D and 3-D multigroup neutron diffusion equations using the finite element method. The developed scripts can simulate reactors with rectangular and hexagonal lattices and have the potential to handle complex core configurations, benefitting from the constructive solid geometry. The meshing subroutine decomposes the domain into unstructured triangular or tetrahedral elements that are either linea...
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#1Khalid Khasawneh (PNU: Pusan National University)
#2Taeho Kim (PNU: Pusan National University)H-Index: 2
Last. Byong-Jo Yun (PNU: Pusan National University)H-Index: 17
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Abstract null null A new model for droplet size prediction in horizontal pipes under stratified and annular flow is presented. The developed model takes into account the effects of the gas velocity, liquid velocity, pipe diameter, and developing length on the droplet size. Four experimental databases of droplet size in air-water horizontal flow under atmospheric pressure were used in the model development. The experimental flow conditions of the database covered a pipe diameter range of 2.45–24 ...
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#1J.-M. Labit (Université Paris-Saclay)H-Index: 2
#2N. SeilerH-Index: 1
Last. Elsa Merle (Grenoble Institute of Technology)H-Index: 4
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Abstract null null Reactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex multiphysic transients. They consist in a very fast power excursion in the core, leading to wall temperature excursions. Many experiments have shown that the heat exchanges coefficients during fast transients differ from those in steady-states. The thermal-hydraulic phenomenology of such transients remains complex and some experimental studies allowed to better understand and quantify the heat excha...
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Abstract null null Over the past decade, the need to supplement system-scale simulations of reactor transients with the results of finer simulations (subchannel or CFD) has increased continuously. In many cases, the local phenomena predicted at these scales (such as flow patterns in the core or within inlet/outlet plenums) can affect the overall transient: in that case, then all codes should be run concurrently in a consistent manner in order to obtain a single, “multi-scale” simulation of the t...
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#1Solomon Bello (HEU: Harbin Engineering University)H-Index: 4
#2Puzhen Gao (HEU: Harbin Engineering University)H-Index: 11
Last. Yuqi Lin (HEU: Harbin Engineering University)H-Index: 4
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Abstract null null Flow characteristics during loss of coolant to the heat exchanger (HX) via the secondary loop cold leg of a natural circulation (NC) test facility referred here as loss of heat sink transient (LOHS) in a closed rectangular NC system having a single heated channel at two different heating powers and system pressures has been investigated experimentally. Two LOHS experiments (LOHS-1 and LOHS-2) were conducted in a well dimensioned closed loop NC test facility designed to represe...
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Abstract null null Slug is produced when the roll waves on the liquid surface undergo constructive interference and the resulting wave height increases beyond the critical height. Slug flow is associated with large aeration that develops a sudden surge in pressure and associated mechanical impact on pipe wall and bends. Such phenomena lead to flow accelerated corrosion (FAC) which results in degradation of pipe thickness with time resulting in cracks from where the gas and liquid leaks. Hence, t...
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#1Eun-haeng Lee (Chonnam National University)H-Index: 3
#2Du-Ri Jung (Chonnam National University)
Last. Jae-Min Kim (Chonnam National University)H-Index: 4
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Abstract null null Seismic Analysis of Safety-Related Nuclear Structures (ASCE 4-16) offers a two-step nonlinear soil-structure interaction analysis procedure for seismically base-isolated structures based on the seismic isolation design response spectrum. The two steps are (I) development of seismic isolation design response spectrum at the foundation level of an isolated structure using frequency domain soil–structure interaction (SSI) analysis for an equivalent linear SSI system and (II) nonl...
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#1J. Boffie (University of Massachusetts Lowell)H-Index: 2
#2S.K. Aghara (University of Massachusetts Lowell)H-Index: 2
Last. J. Strandburg (University of Massachusetts Lowell)
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Abstract null null Modeling nuclear reactors for simulating transients can be very challenging for a lot of reasons, e.g. space–time representation, heterogeneity, etc. Reactor-specific design and data may also be required for the facility being analyzed. Although reactor point kinetics theory is usually a method of choice in analyzing such transients, a reactor’s specifications are required to achieve meaningful results. This work describes a unique method for estimating the fuel temperature re...
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#1Rogelio CastilloH-Index: 4
#2Gustavo Alonso (IPN: Instituto Politécnico Nacional)H-Index: 77
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Abstract null null Recycling in thermal reactors is an alternative that could help to reduce minor actinide inventories produced by depleted fuel assemblies of nuclear reactors; the current paper assesses two proposed BWR fuel assemblies to recycle MA. These fuel designs aim to no introduce any perturbation in the electricity production from the Boiling Water Reactor, and they must satisfy the reactor core safety constraints. Such constraints must be considered under steady and transient conditi...
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Abstract null null The study evaluates the optimal thicknesses of the coating layers of an 800-μm UO2 tri-structural isotropic coated fuel particle (TRISO) for a 10-MWth block-type micro modular high temperature gas-cooled reactor (HTGR) using a response surface methodology (RSM) and an HTGR fuel performance analysis code, COPA. The objective function to be minimized in the optimal design of a TRISO consists of the product of the packing fraction of TRISO particles in a compact, the fractional r...
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