Preliminary Design Analysis of a Hot Gas Ducts for the Nuclear Hydrogen System

Author(s):  
Kee-Nam Song ◽  
Yong-Wan Kim

Korea Atomic Energy Research Institute (KAERI) is in the process of carrying out a nuclear hydrogen system by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950 °C. A coaxial double-tube hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger (IHX) for the nuclear hydrogen system. Recently, a preliminary design analysis for the primary and secondary hot gas ducts of the nuclear hydrogen system was carried out. These preliminary design activities include a preliminary decision on the geometric dimensions, a preliminary strength evaluation and an appropriate material selection. In this study, a preliminary strength evaluation for the HGDs of the nuclear hydrogen system has been undertaken. Preliminary strength evaluation results for the HGDs showed that the geometric dimensions of the proposed HGDs would be acceptable for the design requirements.

2008 ◽  
Vol 131 (1) ◽  
Author(s):  
Kee-nam Song ◽  
Yong-wan Kim

Korea Atomic Energy Research Institute is in the process of carrying out a nuclear hydrogen system by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950°C. A coaxial double-tube hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger for the nuclear hydrogen system. Recently, a preliminary design analysis for the primary and secondary hot gas ducts of the nuclear hydrogen system was carried out. These preliminary design activities include a preliminary decision on the geometric dimensions, a preliminary strength evaluation, and an appropriate material selection. In this study, a preliminary strength evaluation for the HGDs of the nuclear hydrogen system has been undertaken. Preliminary strength evaluation results for the HGDs showed that the geometric dimensions of the proposed HGDs would be acceptable for the design requirements.


2008 ◽  
Vol 33-37 ◽  
pp. 1227-1232
Author(s):  
Kee Nam Song ◽  
Hyeong Yeon Lee ◽  
Yong Wan Kim ◽  
Soo Bum Lee

Korea Atomic Energy Research Institute (KAERI) is in the process of carrying out a Nuclear Hydrogen Development and Demonstration (NHDD) Program by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950°C. A coaxial doubletube hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger (IHX) for the NHDD program. Recently, a preliminary design evaluation for the hot gas duct of the NHDD program was carried out. These preliminary design activities include a preliminary decision on the geometric dimensions, a preliminary strength evaluation, an appropriate material selection, and identifying the design code for the HGD. In this study, a preliminary strength evaluation for the HGD of the NHDD program has been undertaken based on the HTR-10 design concepts. Also, a preliminary evaluation of the creep-fatigue damage for a high temperature HGD structure has been carried out according to the draft code case for Alloy 617. Preliminary strength evaluation results for the HGD showed that the geometric dimensions of the proposed HGD would be acceptable for the design requirements.


Author(s):  
Kee-Nam Song ◽  
Yong-Wan Kim

Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source for a nuclear hydrogen generation. The VHTR can produce hydrogen from heat and water by using a thermo-chemical process or from heat, water, and natural gas by steam reformer technology. Korea Atomic Energy Research Institute (KAERI) is in the process of carrying out a nuclear hydrogen system by considering the indirect cycle gas cooled reactors that produce heat at temperatures in the order of 950°. The nuclear hydrogen system is planning to produce hydrogen by using nuclear energy and a thermo-chemical process. Helium gas is the choice for the coolant of the nuclear hydrogen system since it is an inert gas, with no affinity to a chemical or nuclear activity; therefore a radioactivity transport in the primary circuit of the nuclear hydrogen system is minimal under a normal operation. Moreover, its gaseous nature avoids problems related to a phase change and water-metal reactions and therefore improves its safety. A coaxial double-tube hot gas duct (HGD) is a key component connecting the reactor pressure vessel and the intermediate heat exchanger (IHX) for the nuclear hydrogen system. In this study, a preliminary design analysis for the primary and secondary HGDs of the nuclear hydrogen system was carried out. These preliminary design activities include a preliminary decision on the geometric dimensions, a preliminary strength evaluation and an appropriate material selection. A preliminary decision on the geometric dimensions of the HGDs was undertaken based on three engineering concepts, such as a constant flow velocity model (CFV model), a constant flow rate model (CFR model), a constant hydraulic head model (CHH model), and also based on a heat balanced model (HB model). We compared the geometric dimensions and their preliminary strength evaluation results from the various models.


2018 ◽  
Vol 90 (3) ◽  
pp. 532-541 ◽  
Author(s):  
Francesco Danzi ◽  
Giacomo Frulla ◽  
Giulio Romeo

Purpose This paper aims to present a systematic performance-oriented procedure to predict structural responses of composite layered structures. The procedure has a direct application in the preliminary design of aerospace composite structures evaluating the right and most effective material. Design/methodology/approach The aforementioned procedure is based upon the definition of stiffness invariants. In the paper, the authors briefly recall the definition and the physical explanation of the invariants, i.e. the trace; then they present the scaling procedure for the selection of the best material for a fixed geometrical shape. Findings The authors report the basic principles of the scaling procedure and several examples pertaining typical responses sought in the preliminary design of aeronautic structures Research limitations/implications Typically, during early stages, engineers had to perform the daunting task of balancing among functional requirements and constraints and give the optimum solution in terms of structural concept and material selection. Moreover, preliminary design activities require evaluating different responses as a function of as less as possible parameters, ensuring medium to high fidelity. The importance of incorporating as much physics and understanding of the problem as early as possible in the preliminary design stages is therefore fundamental. A robust and systematic procedure is necessary. Practical implications The time/effort reduction in the preliminary design of composite structures can increase the overall quality of the configuration chosen. Social implications Reduction in design costs and time. Originality/value In spite of the well-known invariant properties of composites, the application and extension to the preliminary design of composite structures by means of a scaling rule is new and original.


Author(s):  
Kee-nam Song ◽  
Yong-wan Kim ◽  
S.-C. Park

The Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source of the order of 950°C for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting the reactor pressure vessel and the intermediate heat exchanger in a VHTR. In this study, a structural sizing methodology for the primary HGD of a VHTR is suggested in order to modulate a flow-induced vibration (FIV). And as an example, a structural sizing of a horizontal HGD with a coaxial double-tube structure was carried out using the suggested method. These activities include a decision of the geometric dimensions, a selection of the material, and a evaluation of the strength of the coaxial double-tube type cross vessel components. Also in order to compare the FIV characteristics of the proposed design cases, a fluid-structure interaction (FSI) analysis on a quarter part of the HGD was carried out using the ADINA code.


2021 ◽  
Vol 57 (1) ◽  
pp. 397-408
Author(s):  
Roberto Rocca ◽  
Fabio Giulii Capponi ◽  
Giulio De Donato ◽  
Savvas Papadopoulos ◽  
Federico Caricchi ◽  
...  

2011 ◽  
Vol 10 (01) ◽  
pp. 69-76 ◽  
Author(s):  
XUDONG DAI ◽  
XUEFEN MA ◽  
YOUBAI XIE

For the definition of knowledge flow, knowledge-flow control and knowledge-acquisition in integrated product design within distributed knowledge resources environment, this paper studies the structural modeling of design activity for integrated product design. The common features of integrated design in distributed resources environment are summarized as follows: centering on specific design requirements, organizing related design resources to perform design activities, outputting design results, carrying on value analysis of design results, and then making design decisions on the basis of value analysis. Based on the common features, a structural model of integrated design activities in distributed resources environment is built, which presents the structural expression of knowledge flow by defining the design requirements, the design resource input, the result output, the design activities, the relationship between the design activities, and the values of the design activities. Design activities at different levels are defined according to the design process models at different levels. A design activity that has been defined can be packaged into design components. The essence of integrated design lies in knowledge integration, which is to be realized by defining the input and output relationship between the design components and the knowledge components.


1972 ◽  
Vol 9 (02) ◽  
pp. 205-215
Author(s):  
william G. Bullock ◽  
Frank D. Yonika

This paper is a summary of a report prepared by the Office of Ship Construction to provide a base reference document from which a detailed design for an automated steam propulsion plant will be developed for unattended engine room operation. As the design details are developed, it may be anticipated that some of the concepts and preliminary design requirements discussed herein may be modified and/or changed to reflect these developments. It should also be noted that the concepts and opinions expressed herein are those of the authors and do not necessarily reflect those of the Maritime Administration.


2020 ◽  
Vol 19 (04) ◽  
pp. 675-699
Author(s):  
Abadi Chaimae ◽  
Abadi Asmae ◽  
Manssouri Imad

Nowadays, industries face very strong challenges because of the high competitiveness between them. In fact, they are required to offer products with high quality and minimum cost in the minimum time. Since most of the characteristics and costs of the product and its manufacturing process are fixed in the design phase, this paper is focused on this strategic phase. Indeed, a new integrated product design approach is presented. It considers at the same time design requirements, materials characteristics, manufacturing parameters and the assembly process specifications. The developed approach is quantitative. Actually, the decision making is based on all its steps on objective and subjective indicators. To validate the integrated approach, a case study on the Schrader Robot is developed. This application allows to choose the most appropriate materials, manufacturing processes and assembly solution of its different components.


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