Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads

Jin Weon Kim, Ik Hyun Song, Hyeong Do Kweon, Jong Sung Kim, Yun-Jae Kim

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

This study designed a specimen that can simulate deformation and crack initiation in system, structure, and components (SSCs) of nuclear power plants (NPPs) under excessive seismic loads, and conducted ultimate strength tests using this specimen at room temperature (RT) and 316°C. The specimen designed was a compact tension (CT) type with a round notch, and both SA312 TP316 stainless steel (SS) and SA508 Gr.3 Cl.1 low-alloy steel (LAS) were used in the experiment. Displacement-controlled cyclic loads with constant and random amplitudes were applied as input loads for the test. One set of input loads consisted of 20 cycles, and the input amplitudes of load-line displacement (LLD) were determined to induce the maximum elastic stress of 6∼ 42Sm on the specimen, where Sm is allowable design stress intensity. The input LLD had a triangular waveform and was fully reversed for both types of amplitude. During the test, multiple sets of input cyclic loads, with increasing amplitude of input LLD, were applied to the specimen until a crack was initiated. The results demonstrated that the specimen used in this study adequately simulates the deformation and failure behaviors of SSCs under excessive seismic loads. In addition, the samples in both materials failed under cyclic load levels that were several times higher than those of design basis earthquake (DBE). The SA316 TP316 SS specimen had a greater safety margin under excessive seismic loading conditions than SA508 Gr.3 Cl.1 LAS specimen, regardless of test temperature.

Original languageEnglish
Title of host publicationDesign and Analysis
PublisherAmerican Society of Mechanical Engineers (ASME)
Volume3A
ISBN (Electronic)9780791851623
DOIs
Publication statusPublished - 2018 Jan 1
EventASME 2018 Pressure Vessels and Piping Conference, PVP 2018 - Prague, Czech Republic
Duration: 2018 Jul 152018 Jul 20

Other

OtherASME 2018 Pressure Vessels and Piping Conference, PVP 2018
CountryCzech Republic
CityPrague
Period18/7/1518/7/20

Fingerprint

Cyclic loads
High strength steel
Stainless steel
Crack initiation
Nuclear power plants
Earthquakes
Cracks
Temperature
Experiments

ASJC Scopus subject areas

  • Mechanical Engineering

Cite this

Kim, J. W., Song, I. H., Kweon, H. D., Kim, J. S., & Kim, Y-J. (2018). Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads. In Design and Analysis (Vol. 3A). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2018-84576

Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads. / Kim, Jin Weon; Song, Ik Hyun; Kweon, Hyeong Do; Kim, Jong Sung; Kim, Yun-Jae.

Design and Analysis. Vol. 3A American Society of Mechanical Engineers (ASME), 2018.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Kim, JW, Song, IH, Kweon, HD, Kim, JS & Kim, Y-J 2018, Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads. in Design and Analysis. vol. 3A, American Society of Mechanical Engineers (ASME), ASME 2018 Pressure Vessels and Piping Conference, PVP 2018, Prague, Czech Republic, 18/7/15. https://doi.org/10.1115/PVP2018-84576
Kim JW, Song IH, Kweon HD, Kim JS, Kim Y-J. Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads. In Design and Analysis. Vol. 3A. American Society of Mechanical Engineers (ASME). 2018 https://doi.org/10.1115/PVP2018-84576
Kim, Jin Weon ; Song, Ik Hyun ; Kweon, Hyeong Do ; Kim, Jong Sung ; Kim, Yun-Jae. / Evaluation of deformation and fracture behaviors of nuclear components using a simulated specimen under excessive seismic loads. Design and Analysis. Vol. 3A American Society of Mechanical Engineers (ASME), 2018.
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