Zobrazeno 1 - 10
of 50
pro vyhledávání: '"Jae-Hyuk Eoh"'
Elevated temperature design and integrity evaluation of a large-scale sodium test facility, STELLA-2
Publikováno v:
Nuclear Engineering and Design. 346:54-66
The construction of a large-scale sodium thermal-hydraulic test facility known as STELLA-2 for use in integral effect tests of a sodium-cooled fast reactor (SFR) at the Korea Atomic Energy Research Institute (KAERI) is scheduled to be completed by th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d11e3eb24e0d426e2d633db3e2da33d
https://doi.org/10.1016/j.nucengdes.2019.02.024
https://doi.org/10.1016/j.nucengdes.2019.02.024
Publikováno v:
Nuclear Engineering and Design. 340:62-67
In Prototype Gen IV Sodium-cooled Fast Reactor (PGSFR), there are two types of sodium-to-sodium heat exchanger, namely, Intermediate Heat Exchanger (IHX) and Decay Heat Exchanger (DHX). The role, function, and size of each heat exchanger are differen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0fbdfb63abb0c8f5707ab2682b6cc515
https://doi.org/10.1016/j.nucengdes.2018.09.026
https://doi.org/10.1016/j.nucengdes.2018.09.026
Autor:
Jung Yoon, Jewhan Lee, Hyungmo Kim, Jae-Hyuk Eoh, Ji-Young Jeong, Chang-Hwan Shin, Sun-Joon Byun
Publikováno v:
Nuclear Engineering and Design. 339:105-115
In this study, single-phase heat transfer characteristics for downstream flow in the support grid of 6 × 6 rod bundle were investigated. It is known that turbulence generated by a support grid with split mixing vanes enhances heat transfer in a rod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::746ba367dbcb606750d3ae4ee0ada2c7
https://doi.org/10.1016/j.nucengdes.2018.09.004
https://doi.org/10.1016/j.nucengdes.2018.09.004
Autor:
Yong-Bum Lee, Jewhan Lee, Eui-Kwang Kim, Kwi Lim Lee, Ji-Young Jeong, Hyungmo Kim, Jae-Ho Jeong, Jae-Hyuk Eoh, Jung Yoon
Publikováno v:
Annals of Nuclear Energy. 120:845-856
The STELLA program is one of the key activities to support the development of PGSFR in Korea and the target is the DHRS. The STELLA-2 facility is an integral effect test facility and scaled-down components of PGSFR are included. For the STELLA-2 desi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd50fcde6a25ecfb9f6cecb2b033b506
https://doi.org/10.1016/j.anucene.2018.07.006
https://doi.org/10.1016/j.anucene.2018.07.006
Publikováno v:
Journal of Nuclear Science and Technology. 54:1065-1073
The design of a sodium-cooled fast reactor (SFR) head can be complicated due to its shape and functions. The head is a component placed in the pressure boundary to shield nuclear radioactive radiation. At the same time, it needs to seal the reactor v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::053098c49f194dc2de3c3e8a2be42967
https://doi.org/10.1080/00223131.2017.1344581
https://doi.org/10.1080/00223131.2017.1344581
Publikováno v:
Nuclear Engineering and Design. 313:73-83
The STELLA-1 facility was designed and constructed to carry out separate effect tests of the decay heat exchanger (DHX) and natural draft sodium-to-air heat exchanger (AHX), which are key components of the safety-grade decay heat removal system in PG
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::78d0eeac6c49b9a00cd13d127a12909b
https://doi.org/10.1016/j.nucengdes.2016.11.035
https://doi.org/10.1016/j.nucengdes.2016.11.035
Publikováno v:
Nuclear Engineering and Design. 371:110963
Multiple studies have been conducted on the convective heat transfer of a liquid metal flow to present the correlations between the Nusselt and Peclet numbers. However, those correlations are considerably deviated from the experimental data obtained
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7b072f075322c48c073a7f59118ff1d1
https://doi.org/10.1016/j.nucengdes.2020.110963
https://doi.org/10.1016/j.nucengdes.2020.110963
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 40:775-782
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c2fb43896fdf70368e2433c6045a57e6
https://doi.org/10.3795/ksme-a.2016.40.9.775
https://doi.org/10.3795/ksme-a.2016.40.9.775
Publikováno v:
Nuclear Engineering and Design. 365:110717
In the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR), a Reactor Vault Cooling System (RVCS) is prepared to maintain the structural integrity of the reactor vessel and the concrete during normal operation as well as to mitigate accidents during
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf669951b2867fbaa797230edf328a46
https://doi.org/10.1016/j.nucengdes.2020.110717
https://doi.org/10.1016/j.nucengdes.2020.110717
Autor:
Jae-Hyuk Eoh, Young-Sang Joo, Hoe-Woong Kim, Florian Le Bourdais, Alexandre Imperiale, Sang-Jin Park, Arnaud Recoquillay
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2020, 365, pp.110688-. ⟨10.1016/j.nucengdes.2020.110688⟩
Nuclear Engineering and Design, Elsevier, 2020, 365, pp.110688-. ⟨10.1016/j.nucengdes.2020.110688⟩
This paper presents a collaborative work that started out under the framework of the Generation IV International Forum regarding ultrasound telemetry in sodium-cooled fast reactors. The liquid sodium environment imposes harsh constraints on immersed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d6cd3682e9885d59f9338dd783bf8409
https://doi.org/10.1016/j.nucengdes.2020.110688
https://doi.org/10.1016/j.nucengdes.2020.110688