scholarly journals STRESS ANALYSIS OF A REACTOR CORE SUPPORT STRUCTURE CONSISTING OF TWO INTERCONNECTED MULTIREGION PLATES.

1968 ◽  
Author(s):  
A.H. Marchertas
Keyword(s):  
Stress Analysis ◽  
Reactor Core ◽  
Support Structure

scholarly journals ROUTING DESIGN ON THE PRIMARY COOLING PIPING SYSTEM IN PLATE-TYPE CONVERTED TRIGA 2000 REACTOR BANDUNG

2019 ◽  
Vol 21 (3) ◽  
pp. 107
Author(s):  
Veronica Indriati Sri Wardhani ◽  
Henky Poedjo Rahardjo ◽  
Rasito Tursinah
Keyword(s):  
Stress Analysis ◽  
Cooling System ◽  
Flow Direction ◽  
Reactor Core ◽  
Working Fluid ◽  
Piping System ◽  
Research Activities ◽  
Routing Design ◽  
Core Cooling ◽  
Plate Type

In 2015, research activities to modify TRIGA 2000 Reactor Bandung fuel element from cylindrical to plate-type have been initiated. By using plate-type fuel elements, core cooling process will be altered due to different generated heat distribution. The direction of cooling flow is changed from bottom-to-top natural convection to top-to-bottom forced convection. This change of flow direction requires adjustment on the cooling piping system, in order to produce simple, economical, and safe piping route. This paper will discuss the design of suitable piping routing based on pipe stress and N-16 radioactivity. The design process was carried out in several stages which include thermal-hydraulic data of reactor core to determine the process variables, followed by modeling various pipeline routes. Based on available space and ease of manufacture, four possible alternative routings were determined. Four routings were produced and analyzed to minimize the amount of N-16 radioactivity on the surface of the reactor tank, prolonging the cooling fluid travel time to reach at least five times of N-16 half-life. Subsequent pipe stress analysis using CAESAR II software was conducted to ensure that the piping system will be able to withstand various loads such as working fluid load, pipe weight, along with working temperature and pressure. The results showed that the occurred stresses were still below the safety limit as required in ASME B31.1 Code, indicated that the designed and selected pipeline routing of primary cooling system in the Plate-type Converted TRIGA 2000 Reactor Bandung has met the safety standards.Keywords: TRIGA reactor, Cooling system modification, Pipeline routing design, Pipe stress analysis, N-16 radioactivity

Design and Stress Analysis of Support Structure of Toroidal Field Coil for the JT-60SC

2004 ◽  
Vol 14 (2) ◽  
pp. 1427-1430 ◽  
Author(s):  
K. Tsuchiya ◽  
K. Kizu ◽  
Y.M. Miura ◽  
T. Ando ◽  
A. Sakasai ◽  
...  
Keyword(s):  
Stress Analysis ◽  
Toroidal Field ◽  
Support Structure ◽  
Field Coil

Stress Analysis and Structural Integrity Evaluations of Pressure Vessel in Molten Salt Reactor

2016 ◽  
Author(s):  
Xiaoyan Wang ◽  
Shifeng Zhu ◽  
Xiao Wang ◽  
Yun Cao
Keyword(s):  
Stress Analysis ◽  
Molten Salt ◽  
Pressure Vessel ◽  
Nuclear Reactor ◽  
Structural Integrity ◽  
Reactor Core ◽  
Safety Evaluation ◽  
Molten Salt Reactor ◽  
Fine Mesh ◽  
Creep Fatigue

To guarantee the safety of nuclear reactor, the stress analysis and structural integrity evaluations of the reactor pressure vessel (RPV) are very important for Thorium-based Molten Salt Reactor (TMSR), whose design temperature and design pressure are 700 °C and 0.5MPa respectively. In this paper, the structural analysis is firstly carried out by using a 3D coarse model of the RPV. Secondly, the reactor core support are recalculated by a sub-model with a fine mesh and the analysis results are evaluated according to ASME NH code, including stress evaluation, strain and deformation evaluation and creep-fatigue evaluation. It was found that the initial structural did not meet the requirements of creep-fatigue limits. Finally, structural optimization designs are proposed, such as T-shaped modified structure and fillet design, whose results can satisfy the requirements of creep-fatigue limits. These analysis methods and results provide some practical engineering guidance to the structural design and safety evaluation of the RPV in TMSR.

scholarly journals Design and Optimization of Robot Support Structure for Inverted Operation

2019 ◽  
Vol 9 (2) ◽  
pp. 1596-1600
Keyword(s):  
Boundary Conditions ◽  
Stress Analysis ◽  
Rapid Development ◽  
Emergency Operation ◽  
New Method ◽  
Total Deformation ◽  
Support Structure ◽  
Design And Optimization ◽  
3D Geometry

In this paper we present an new method for optimization of robot structure for inverted operations, as rapid development is seen in the fields of robotics, robots are being designed for different operations. Robots move with higher speeds & create inertia loads, & during emergency operation there is sudden spike in load & the robot support structure needs to accommodate these loads. In this project we are analyze the robot support structure. Robot support structure means the main supportive member which is the base of the robot and it gives support as well as stabilization to the robot. 3D geometry of robot support structure is designed as per dimension in the workbench by using ANSYS 16.0. Upon applying boundary conditions such as robot weight, forces applied to his body and moments applied to the structure of the robot support. Following this, stress analysis, von-misses stress, total deformation of the structure of the robot support.

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