An Innovative Three-Dimensional Heterogeneous Coarse-Mesh Transport Method for Advanced and Generation IV Reactor Core Analysis and Design

A three dimensional structural collapse analysis computer program is described, and illustrated by reference to a safety vehicle structure analysed and designed using the program. The particular problems of large displacements and material non-linearity are accounted for, and a method of estimating the permanent set which results after impact is described. Based on an incremental formulation of the conventional finite-element method, the computer program is capable of tracing the complete load deflection characteristics of a structure up to and beyond the point of collapse.

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A numerical three-dimensional viscous transonic wing-body analysis and design tool

10.2514/6.1978-101 ◽

1978 ◽

Cited By ~ 5

Author(s):

W. MASON ◽

D. MACKENZIE ◽

M. STERN ◽

J. JOHNSON

Keyword(s):

Three Dimensional ◽

Design Tool ◽

Analysis And Design

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Positron Emission Tomography (PET) for Flow Measurement

Advanced Materials Research ◽

10.4028/www.scientific.net/amr.301-303.1316 ◽

2011 ◽

Vol 301-303 ◽

pp. 1316-1321 ◽

Cited By ~ 1

Author(s):

Arthur E. Ruggles ◽

Bi Yao Zhang ◽

Spero M. Peters

Keyword(s):

Positron Emission Tomography ◽

Pet Imaging ◽

Three Dimensional ◽

Bulk Water ◽

Emission Tomography ◽

Optical Methods ◽

Imaging Method ◽

Analysis And Design ◽

Pet Tracer ◽

Positron Emission

Positron Emission Tomography (PET) produces a three dimensional spatial distribution of positron-electron annihilations within an image volume. Various positron emitters are available for use in aqueous, organic and liquid metal flows. Preliminary experiments at the University of Tennessee at Knoxville (UTK) injected small flows of PET tracer into a bulk water flow in a four rod bundle. The trajectory and diffusion of the tracer in the bulk flow were then mapped using a PET scanner. A spatial resolution of 1.4 mm is achieved with current preclinical Micro-PET imaging equipment resulting in 200 MB 3D activity fields. A time resolved 3-D spatial activity profile was also measured. The PET imaging method is especially well suited to complex geometries where traditional optical methods such as LDV and PIV are difficult to apply. PET methods are uniquely useful for imaging in opaque fluids, opaque pressure boundaries, and multiphase studies. Several commercial and shareware Computational Fluid Dynamics (CFD) codes are currently used for science and engineering analysis and design. These codes produce detailed three dimensional flow predictions. The models produced by these codes are often difficult to validate. The development of this experimental technique offers a modality for the comparison of CFD outcomes with experimental data. Developed data sets from PET can be used in verification and validation exercises of simulation outcomes.

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A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL

10.1115/icone28-64912 ◽

2021 ◽

Author(s):

Wen Yang ◽

Lun Zhou ◽

Junrong Qiu ◽

Yun Tai

Keyword(s):

Density Distribution ◽

Power Distribution ◽

Channel Model ◽

Three Dimensional ◽

Least Square ◽

Object Oriented Programming ◽

Core Analysis ◽

Fuel Temperature ◽

Fuel Assemblies ◽

Calculation Results

Abstract Three dimensional PWR-core analysis code CORAL is developed by Wuhan Second Ship Design and Research Institute. This code provides basic functions including three-dimensional power distribution, fine power reconstruction, fuel temperature distribution, critical search, control rod worth, reactivity coefficients, burnup and nuclide density distribution, etc. CORAL employ nodal expansion method to solve neutron diffusion equation, and the least square method is used to achieve few group constants, and sub-channel model and one-dimensional heat transfer is used to calculate fuel temperature and coolant density distribution, and burnup distribution and nuclide nuclear density could be obtained by solving macro-depletion and micro-depletion equation. The CORAL code is convenient to update and maintain in consider of modular, object-oriented programming technology. In order to analyze the computational accuracy of the CORAL code in small PWR-core and its capability to deal with heterogeneous, calculation analysis are carried out based on the material and geometry parameters of the SMART core. The core has 57 fuel assemblies, with 8, 20 or 24 gadolinium rods arranged in the fuel assemblies. In this paper, a quantitative comparison and analysis of the small PWR problem calculation results are carried out. Numerical results, including effective multiplication factor, assembly power distribution and pin power distribution, all agree well with the calculation results of OpenMC or Bamboo at both hot zero-power (HZP) and hot full-power (HFP) conditions.

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ANALYSIS AND DESIGN OF G+4 RESIDENTIAL BUILDING USING ETABS

International Journal of Engineering Applied Sciences and Technology ◽

10.33564/ijeast.2021.v05i12.044 ◽

2021 ◽

Vol 5 (12) ◽

Author(s):

Chinmay Padole ◽

Samiksha Bansod ◽

Taniya Sukhdeve ◽

Abhishek Dhomne ◽

Maheshwari Nagose ◽

...

Keyword(s):

Three Dimensional ◽

Residential Building ◽

Shape Modelling ◽

Analysis And Design ◽

Design Procedures ◽

High Rise ◽

Building Systems ◽

Dynamic Loadings ◽

Storey Building

ETABS stands for Extended Three-Dimensional Analysis of Building Systems. ETABS is commonly used to analyze: Skyscrapers, concrete structures, low and high rise buildings, and portal frame structures. The case study in this paper mainly emphasizes on structural behavior of multi-storey building for different plan configurations like rectangular, C, L and I-shape. Modelling of 15-storeys R.C.C. framed building is done on the ETABS software for analysis ETABS issue, for analysis and design for building systems. ETABS features are contain powerful graphical interface coupled with unmatched modeling, analytical, and design procedures, all integrated using a common database. STAAD and ETABS both of the software are well equipped and very much capable of handling different shape of the structures, static and dynamic loadings and different material properties.

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Criticality Calculations and Basic Sensitivity/Uncertainty Investigation of LR-0 Benchmark Core

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4041692 ◽

2019 ◽

Vol 5 (3) ◽

Cited By ~ 1

Author(s):

Tomáš Czakoj ◽

Evžen Losa

Keyword(s):

Lithium Fluoride ◽

Three Dimensional ◽

Reactor Core ◽

Nuclear Data ◽

Monte Carlo Code ◽

Multiplication Factor ◽

Reference Case ◽

Energy Version ◽

Data Libraries ◽

Nuclear Data Libraries

Three-dimensional Monte Carlo code KENO-VI of SCALE-6.2.2 code system was applied for criticality calculation of the LR-0 reactor core. A central module placed in the center of the core was filled by graphite, lithium fluoride-beryllium fluoride (FLIBE), and lithium fluoride-sodium fluoride (FLINA) compounds. The multiplication factor was obtained for all cases using both ENDF/B-VII.0 and ENDF/B-VII.1 nuclear data libraries. Obtained results were compared with benchmark calculations in the MCNP6 using ENDF/B-VII.0 library. The results of KENO-VI calculations are found to be in good agreement with results obtained by the MCNP6. The discrepancies are typically within tens of pcm excluding the case with the FLINA filling. Sensitivities and uncertainties of the reference case with no filling were determined by a continuos-energy version of the TSUNAMI sequence of SCALE-6.2.2. The obtained uncertainty in multiplication factor due to the uncertainties in nuclear data is about 650 pcm with ENDF/B-VII.1.

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