Technical Briefs

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

[+] Author and Article Information
Kee-nam Song

 Korea Atomic Energy Research Institute (KAERI), P.O. BOX 105, Yuseong-gu, Daejeon 305-353, Koreaknsong@kaeri.re.kr

Yong-wan Kim

 Korea Atomic Energy Research Institute (KAERI), P.O. BOX 105, Yuseong-gu, Daejeon 305-353, Korea

J. Eng. Gas Turbines Power 131(1), 014501 (Oct 02, 2008) (4 pages) doi:10.1115/1.2983141 History: Received July 27, 2008; Revised July 30, 2008; Published October 02, 2008

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.

Copyright © 2009 by American Society of Mechanical Engineers
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Grahic Jump Location
Figure 1

Nuclear hydrogen system

Grahic Jump Location
Figure 2

Position of the primary HGD

Grahic Jump Location
Figure 3

Cross section of the primary HGD

Grahic Jump Location
Figure 4

Cross section of the secondary HGD



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