Research Papers: Design and Analysis

An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant

[+] Author and Article Information
Hyeong-Yeon Lee1

 Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Koreahylee@kaeri.re.kr

Kee-Nam Song, Yong-Wan Kim, Sung-Deok Hong

 Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea

Hong-Yune Park

 AD-Solution Co., Ltd., 1101 Hanjin Officetel 535-5, Bongmyoung-dong Yusong-gu, Daejeon 305-301, Republic of Korea


Corresponding author.

J. Pressure Vessel Technol 133(5), 051208 (Jul 14, 2011) (7 pages) doi:10.1115/1.4003466 History: Received May 10, 2010; Revised January 04, 2011; Published July 14, 2011; Online July 14, 2011

A process heat exchanger (PHE) transfers the heat generated from a nuclear reactor to a sulfur-iodine hydrogen production system in the Nuclear Hydrogen Development and Demonstration, and was subjected to very high temperature up to 950°C. An evaluation of creep-fatigue damage, for a prototype PHE, has been carried out from finite element analysis with the full three dimensional model of the PHE. The inlet temperature in the primary side of the PHE was 950°C with an internal pressure of 7 MPa, while the inlet temperature in the secondary side of the PHE is 500°C with internal pressure of 4 MPa. The candidate materials of the PHE were Alloy 617 and Hastelloy X. In this study, only the Alloy 617 was considered because the high temperature design code is available only for Alloy 617. Using the full 3D finite element analysis on the PHE model, creep-fatigue damage evaluation at very high temperature was carried out, according to the ASME Draft Code Case for Alloy 617, and technical issues in the Draft Code Case were raised.

Copyright © 2011 by American Society of Mechanical Engineers
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Figure 7

Flow directions of primary and secondary coolants

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Figure 10

Pipes connected to PHE and end condition

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Figure 8

Primary coolant flow (He gas)

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Figure 9

Secondary coolant flow (SO2)

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Figure 11

Full heat transfer FE model and temperature distributions of the PHE internal sections

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Figure 12

Temperature distributions of the pressure boundary of the PHE

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Figure 13

Thermal stress distributions of the PHE

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Figure 14

Thermal stress distributions near the primary inlet pipe

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Figure 15

Creep-fatigue damage envelope for Alloy 617

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Figure 1

Conceptual layout of a nuclear hydrogen production system

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Figure 2

Prototype of process heat exchanger

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Figure 3

Components of process heat exchanger

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Figure 4

Machined single plate in a laboratory scale mock-up heat exchanger

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Figure 5

Laboratory scale mock-up heat exchanger for the test

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Figure 6

Flow paths of primary and secondary coolants



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