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

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-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 languageEnglish
Title of host publicationDesign and Analysis
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791850398
DOIs
StatePublished - 2016
EventASME 2016 Pressure Vessels and Piping Conference, PVP 2016 - Vancouver, Canada
Duration: 17 Jul 201621 Jul 2016

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume3
ISSN (Print)0277-027X

Conference

ConferenceASME 2016 Pressure Vessels and Piping Conference, PVP 2016
Country/TerritoryCanada
CityVancouver
Period17/07/1621/07/16

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