scholarly journals BUGJEFF311.BOLIB (JEFF-3.1.1) and BUGENDF70.BOLIB (ENDF/B-VII.0) – Generation Methodology and Preliminary Testing of two ENEA-Bologna Group Cross Section Libraries for LWR Shielding and Pressure Vessel Dosimetry

2016 ◽  
Vol 106 ◽  
pp. 04009
Author(s):  
Massimo Pescarini ◽  
Valentin Sinitsa ◽  
Roberto Orsi ◽  
Manuela Frisoni
Keyword(s):  
Cross Section ◽  
Pressure Vessel ◽  
Preliminary Testing

scholarly journals Deformation and Strength of a Pressure Vessel with Elliptical Cross Section

1968 ◽  
Vol 11 (48) ◽  
pp. 1015-1026 ◽  
Author(s):  
Koki MIZOGUCHI ◽  
Kaoru SHIRAKAWA ◽  
Shigeru HAYASHI
Keyword(s):  
Cross Section ◽  
Pressure Vessel ◽  
Elliptical Cross Section ◽  
Elliptical Cross

Toroidal uniformly stressed pressure vessel shell formed by the meridian and ring filament winding

2021 ◽  
Author(s):  
M.A. Komkov
Keyword(s):  
High Pressure ◽  
Cross Section ◽  
Pressure Vessel ◽  
Filament Winding ◽  
Industrial Workers ◽  
Equilibrium Equations ◽  
Emergency Situations ◽  
Breathing Apparatus ◽  
Composite Pressure Vessel ◽  
Toroidal Shells

The paper outlines the prospects for the use of composite toroidal high-pressure cylinders for the breathing apparatus of the Ministry of Emergency Situations, fire brigades, industrial workers, which are more ergonomic in comparison with their cylindrical counterparts. Relying on the analytical solution of the equilibrium equations, we determined the shape of the cross-section of toroidal shells reinforced along the meridians and representing intersecting loop-like curves that form an infinitely long corrugated pipe. The study introduces a solution for a toroidal composite pressure vessel formed by the intersection of the upper and lower branches of the shell, reinforced along the meridians, and a profiled ring layer of filaments installed at the point of their intersection. The parameters of the toroidal uniformly stressed pressure vessel shell made by ring and meridian filament winding are calculated.

scholarly journals Modernization of Cross Section Library for VVER-1000 Type Reactors Internals and Pressure Vessel Dosimetry

2016 ◽  
Vol 106 ◽  
pp. 04014 ◽  
Author(s):  
Andrey Voloschenko ◽  
Sergey Zaritskiy ◽  
Aleksander Egorov ◽  
Viktor Boyarinov
Keyword(s):  
Cross Section ◽  
Pressure Vessel

Assessment of Overlapped Internal and External Volumetric Flaws in p-M Diagram

2011 ◽  
Vol 133 (3) ◽  
Author(s):  
Shinji Konosu ◽  
Hikaru Miyata
Keyword(s):  
Finite Element ◽  
Cross Section ◽  
Pressure Vessel ◽  
Effective Cross Section ◽  
Finite Element Analyses ◽  
Diagram Method ◽  
Reference Stress ◽  
Common Problems ◽  
Good Agreement

Assessment of overlapped internal and external volumetric flaws is one of the most common problems related to pressure vessel and piping components. Under the current fitness for service rules, such as those provided in ASME, BS, and so on, the procedures for the assessment of these flaws have not yet been defined. In this paper, a reference stress, incorporating the decrease in the effective cross section as a function of flaw depth and flaw angle in a cylinder, has been proposed in order to assess the flaws using the simple p-M (pressure-moment) diagram method. Numerous finite element analyses for a cylinder with overlapped internal and external flaws were conducted to verify the proposed procedure. There is good agreement among them.

Simplified Thermal Analysis for Embedded Piping

1992 ◽  
Author(s):  
Pirooz M. H. Joodi
Keyword(s):  
Cross Section ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Structural Integrity ◽  
Seismic Analysis ◽  
Elementary Theory ◽  
Thermal Characteristics ◽  
Soil Parameters ◽  
Tubular Structures ◽  
Hollow Beam

Abstract The growing use of tubular structures in nuclear reactor facilities such as pipes, conduits and ducts that are buried underground, requires more detailed stress analysis to demonstrate structural integrity as required by Section III of the Boiler Pressure Vessel Code and other applicable industry codes. Thermal behavior of the pipe and soil interference can be conservatively evaluated by implementing the thermal characteristics and properties of the pipe into the expressions, as deduced by previous studies, which are made for the seismic analysis of buried piping. This paper presents procedures to evaluate the different pipe/soil parameters to be applied in those expressions, and explains these equations from designers perspectives and, finally, suggests an approach to combine various pipe stresses to check against ASME Boiler and Pressure Vessel Code Section III. The analysis assumes that the soil is linearly elastic and homogenous and the structure is a straight slender solid or hollow beam with a uniform, symmetrical cross section that satisfies the conditions of the elementary theory of beams on elastic foundations.

Experimentally-Benchmarked Computational Fluid Dynamics Simulations of an Array of Heated Rods Within a Square-Cross-Section Helium-Filled Pressure Vessel

2016 ◽  
Author(s):  
Dilesh Maharjan ◽  
Mustafa Hadj-Nacer ◽  
Narayana R. Chalasani ◽  
Miles Greiner
Keyword(s):  
Cross Section ◽  
Heat Generation ◽  
Pressure Vessel ◽  
Radiation Heat Transfer ◽  
Used Nuclear Fuel ◽  
Nuclear Fuel Assembly ◽  
Experimental Apparatus ◽  
Induced Motion ◽  
Dynamics Simulations ◽  
Square Array

An experimental apparatus was constructed, consisting of an 8×8 array of electrically-heated rods held in a square array by stainless-steel spacer plates near their ends. The rod/plate assembly was enclosed within a square-cross-section helium-filled aluminum pressure vessel and the rods were oriented vertically. The apparatus simulates the region between two consecutive spacer plates of a used nuclear fuel assembly within a vertical dry storage canister. Rod, spacer plate, and enclosure wall temperatures were measured using thermocouples in a matrix of nine experiments with total rod heat generation rates of 100, 300, and 500 W, and nominal helium pressures of 1, 2, and 3 atm. Steady-state simulations representing the experiment were performed, which include heat generation within the rods, conduction within the solid elements, as well as buoyancy-induced motion within, and natural convection and radiation heat transfer across, helium-filled regions. These were compared to the experimental results to assess the accuracy of the computational model for a range of boundary conditions. The comparison between the simulated and measured data showed that the simulations systematically under predict the hotter rod temperatures and over predict the cooler ones. Linear regression showed that 95% of the simulated temperatures are within 4.26°C of the correlation values.

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