Zobrazeno 1 - 10
of 163
pro vyhledávání: '"Nam-Su Huh"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 9, Pp 3764-3774 (2024)
In accordance with Regulatory Guide 1.207, Rev.1, fatigue assessments must be conducted considering the influence of primary coolant environment in nuclear reactors. Environmental fatigue, resulting from corrosion in the primary coolant, is evaluated
Externí odkaz:
https://doaj.org/article/a2e569e69a15451685114998fbb8335f
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 1-8 (2024)
In this study, the influence of thermal aging on structural integrity is investigated for Gr. 91 steel. A commercial grade Gr. 91 steel is used for the virgin material, and service-exposed Gr. 91 steel is sampled from a steam pipe of a super critical
Externí odkaz:
https://doaj.org/article/b35e920a39514aa6823892f612f95043
Publikováno v:
Applied Sciences, Vol 14, Iss 20, p 9441 (2024)
The interactions between multiple cracks significantly influence fracture mechanics parameters, necessitating their consideration in crack assessments. Codes such as ASME Section XI, API 579, BS 7910, and British Energy R6 provide guidelines for crac
Externí odkaz:
https://doaj.org/article/fdc9b6e3023d45aea664c07320091531
Autor:
Jun-Young Kim, Jong Min Lee, Jun Geun Park, Jong-Sung Kim, Min Ki Cho, Sang Won Ahn, Gyeong-Hoi Koo, Bong Hee Lee, Nam-Su Huh, Yun-Jae Kim, Jong-In Kim, Il-Kwun Nam
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 343-356 (2022)
As a part of round robin analysis to develop a finite element elastic-plastic seismic analysis procedure for nuclear safety class 1 components, a series of parametric analyses was carried out on the simulated pressurizer surge line system model to in
Externí odkaz:
https://doaj.org/article/d646595ee9f9417ebed7ec4dfd3529a4
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 974-987 (2021)
This paper presents ductile fracture simulation of full-scale cracked pipe for nuclear piping materials using the cohesive zone model (CZM). The main objective of this study is to investigate the applicability of CZM to predict ductile fracture of cr
Externí odkaz:
https://doaj.org/article/155d23ae174e4307ba8635e92fe5083b
Autor:
Gi-Bum Lee, Seung-Hyun Park, Youn-Young Jang, Nam-Su Huh, Sung-Hoon Park, Noh-Hwan Park, Jun Park
Publikováno v:
Applied Sciences, Vol 12, Iss 6, p 3075 (2022)
A crack growth simulation program based on the advanced iterative-finite element method (AI-FEM) was developed to predict realistic crack growth of structures. The developed program was suggested to calculate the exact stress intensity factor for arb
Externí odkaz:
https://doaj.org/article/223a249ac6b64350a3125511be481fdb
Autor:
Tae-Hyeon Seok, Nam-Su Huh
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers - A. 47:245-254
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2edfee6790e35c91d5996110fd7a2d97
https://doi.org/10.3795/ksme-a.2023.47.3.245
https://doi.org/10.3795/ksme-a.2023.47.3.245
Autor:
Yun Jae Kim, Jong Min Lee, Nam-Su Huh, Min Ki Cho, Bong Hee Lee, Jun Geun Park, Jong-In Kim, Jong Sung Kim, Sang Won Ahn, Jun-Young Kim, Il-Kwun Nam, Gyeong-Hoi Koo
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 343-356 (2022)
As a part of round robin analysis to develop a finite element elastic-plastic seismic analysis procedure for nuclear safety class 1 components, a series of parametric analyses was carried out on the simulated pressurizer surge line system model to in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f4746685bed8b3ce70b05bb92732c034
http://www.sciencedirect.com/science/article/pii/S1738573321004125
http://www.sciencedirect.com/science/article/pii/S1738573321004125
Autor:
Gi-Bum Lee, Youn-Young Jang, Nam-Su Huh, Sung-Hoon Park, Noh-Hwan Park, Jun Park, Kyoungsoo Park
Publikováno v:
Volume 4A: Materials and Fabrication.
Because of the long-term operation of nuclear power plants, the assessment of crack growth in pipelines has become one of the most important issues. Crack growth resistance in operating nuclear power plants is typically evaluated using linear elastic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7b77e4b02648eb475163d2c971aa447
https://doi.org/10.1115/pvp2022-84684
https://doi.org/10.1115/pvp2022-84684
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 3, Pp 974-987 (2021)
This paper presents ductile fracture simulation of full-scale cracked pipe for nuclear piping materials using the cohesive zone model (CZM). The main objective of this study is to investigate the applicability of CZM to predict ductile fracture of cr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::45ffe311ee38583a4efdcfab8c615465
http://www.sciencedirect.com/science/article/pii/S1738573320308032
http://www.sciencedirect.com/science/article/pii/S1738573320308032