On a design acceptability of 90° elbow according to pipe length at elevated temperature condition

Seong Yun Jeong; Min Gu Won; Jae Boong Choi; Nam Su Huh; Young Jin Oh

doi:10.1115/PVP2016-63317

On a design acceptability of 90° elbow according to pipe length at elevated temperature condition

Seong Yun Jeong
, Min Gu Won
, Jae Boong Choi
, Nam Su Huh
, Young Jin Oh

Dept. of Mechanical System and Design Engineering

Sungkyunkwan University
KEPCO Engineering and Construction Co. Inc.

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

Abstract

Sodium-cooled Fast Reactor, SFR is promising candidate of Generation-IV reactor. SFR is operated at high temperature and low pressure. For reducing high thermal stress, thin-walled components and structures are employed for SFR. However, thins-walled components are vulnerable to seismic damage[1]. In this paper, the structural integrity assessment are performed to investigate the effect of piping length on creep-fatigue and seismic damage at elevated temperature. L-shaped elbow is considered for piping design and finite element analyses are conducted to calculate creep-fatigue and seismic damage. The evaluation of creep fatigue damage is carried out according to the elevated temperature design codes of ASME B&PV Sec. III Subsec. NH-3200[2]. Seismic damage are evaluated based ASME B&PV Sec. III Subsec. NB-3600[3] and ASME B&PV Sec. III Div.5 HBB-3200[4]. From the results of creep-fatigue and seismic damage, limit length of piping is determined.

Original language	English
Title of host publication	Design and Analysis
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Electronic)	9780791850398
DOIs	https://doi.org/10.1115/PVP2016-63317
State	Published - 2016
Event	ASME 2016 Pressure Vessels and Piping Conference, PVP 2016 - Vancouver, Canada Duration: 17 Jul 2016 → 21 Jul 2016

Publication series

Name	American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume	3
ISSN (Print)	0277-027X

Conference

Conference	ASME 2016 Pressure Vessels and Piping Conference, PVP 2016
Country/Territory	Canada
City	Vancouver
Period	17/07/16 → 21/07/16

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 11 Sustainable Cities and Communities

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10.1115/PVP2016-63317

Cite this

Jeong, S. Y., Won, M. G., Choi, J. B., Huh, N. S., & Oh, Y. J. (2016). On a design acceptability of 90° elbow according to pipe length at elevated temperature condition. In Design and Analysis Article V003T03A091 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 3). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2016-63317

@inproceedings{99df32bc834b461a9acd36e2c03f401e,

title = "On a design acceptability of 90° elbow according to pipe length at elevated temperature condition",

abstract = "Sodium-cooled Fast Reactor, SFR is promising candidate of Generation-IV reactor. SFR is operated at high temperature and low pressure. For reducing high thermal stress, thin-walled components and structures are employed for SFR. However, thins-walled components are vulnerable to seismic damage[1]. In this paper, the structural integrity assessment are performed to investigate the effect of piping length on creep-fatigue and seismic damage at elevated temperature. L-shaped elbow is considered for piping design and finite element analyses are conducted to calculate creep-fatigue and seismic damage. The evaluation of creep fatigue damage is carried out according to the elevated temperature design codes of ASME B\&PV Sec. III Subsec. NH-3200[2]. Seismic damage are evaluated based ASME B\&PV Sec. III Subsec. NB-3600[3] and ASME B\&PV Sec. III Div.5 HBB-3200[4]. From the results of creep-fatigue and seismic damage, limit length of piping is determined.",

author = "Jeong, \{Seong Yun\} and Won, \{Min Gu\} and Choi, \{Jae Boong\} and Huh, \{Nam Su\} and Oh, \{Young Jin\}",

note = "Publisher Copyright: Copyright {\textcopyright} 2016 by ASME.; ASME 2016 Pressure Vessels and Piping Conference, PVP 2016 ; Conference date: 17-07-2016 Through 21-07-2016",

year = "2016",

doi = "10.1115/PVP2016-63317",

language = "English",

series = "American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP",

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booktitle = "Design and Analysis",

}

Jeong, SY, Won, MG, Choi, JB, Huh, NS & Oh, YJ 2016, On a design acceptability of 90° elbow according to pipe length at elevated temperature condition. in Design and Analysis., V003T03A091, American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, vol. 3, American Society of Mechanical Engineers (ASME), ASME 2016 Pressure Vessels and Piping Conference, PVP 2016, Vancouver, Canada, 17/07/16. https://doi.org/10.1115/PVP2016-63317

On a design acceptability of 90° elbow according to pipe length at elevated temperature condition. / Jeong, Seong Yun; Won, Min Gu; Choi, Jae Boong et al.
Design and Analysis. American Society of Mechanical Engineers (ASME), 2016. V003T03A091 (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 3).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - On a design acceptability of 90° elbow according to pipe length at elevated temperature condition

AU - Jeong, Seong Yun

AU - Won, Min Gu

AU - Choi, Jae Boong

AU - Huh, Nam Su

AU - Oh, Young Jin

PY - 2016

Y1 - 2016

N2 - Sodium-cooled Fast Reactor, SFR is promising candidate of Generation-IV reactor. SFR is operated at high temperature and low pressure. For reducing high thermal stress, thin-walled components and structures are employed for SFR. However, thins-walled components are vulnerable to seismic damage[1]. In this paper, the structural integrity assessment are performed to investigate the effect of piping length on creep-fatigue and seismic damage at elevated temperature. L-shaped elbow is considered for piping design and finite element analyses are conducted to calculate creep-fatigue and seismic damage. The evaluation of creep fatigue damage is carried out according to the elevated temperature design codes of ASME B&PV Sec. III Subsec. NH-3200[2]. Seismic damage are evaluated based ASME B&PV Sec. III Subsec. NB-3600[3] and ASME B&PV Sec. III Div.5 HBB-3200[4]. From the results of creep-fatigue and seismic damage, limit length of piping is determined.

AB - Sodium-cooled Fast Reactor, SFR is promising candidate of Generation-IV reactor. SFR is operated at high temperature and low pressure. For reducing high thermal stress, thin-walled components and structures are employed for SFR. However, thins-walled components are vulnerable to seismic damage[1]. In this paper, the structural integrity assessment are performed to investigate the effect of piping length on creep-fatigue and seismic damage at elevated temperature. L-shaped elbow is considered for piping design and finite element analyses are conducted to calculate creep-fatigue and seismic damage. The evaluation of creep fatigue damage is carried out according to the elevated temperature design codes of ASME B&PV Sec. III Subsec. NH-3200[2]. Seismic damage are evaluated based ASME B&PV Sec. III Subsec. NB-3600[3] and ASME B&PV Sec. III Div.5 HBB-3200[4]. From the results of creep-fatigue and seismic damage, limit length of piping is determined.

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DO - 10.1115/PVP2016-63317

M3 - Conference contribution

AN - SCOPUS:85006264093

T3 - American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

BT - Design and Analysis

PB - American Society of Mechanical Engineers (ASME)

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ER -

On a design acceptability of 90° elbow according to pipe length at elevated temperature condition

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