Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Soo Hyoung Kim"'
Publikováno v:
한국해양공학회지, Vol 37, Iss 5, Pp 205-214 (2023)
As the regulations on greenhouse gas emissions at sea become strict, efforts are being made to minimize environmental pollutants emitted from fossil fuels used by ships. Considering the large sizes of ships in conjunction with securing stable supplie
Externí odkaz:
https://doaj.org/article/54bd2289af104a2ca52ec395c3c5c13e
Publikováno v:
International Journal of Naval Architecture and Ocean Engineering, Vol 16, Iss , Pp 100588- (2024)
As international maritime trade among countries increases, great efforts are being made to reduce the amount of greenhouse gases emitted from ships using conventional fossil fuels. A variety of environment-friendly power sources for ships are being c
Externí odkaz:
https://doaj.org/article/a2e5931f7d52423eaba899b63224b0d1
Autor:
Hyoung Kyu Cho, Ik Kyu Park, Jae Jun Jeong, Seung Jun Lee, Hyungrae Kim, Soo Hyoung Kim, Han Young Yoon
Publikováno v:
Progress in Nuclear Energy. 77:132-140
CUPID-SG (CUPID code for Steam Generators) is a computer code for analyzing two-phase flows and heat transfer in PWR steam generators. It was derived from CUPID (Component Unstructured Program for Interfacial Dynamics), which is a component-scale the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fc8f185e0a1949398b12fd7a5494e8a1
https://doi.org/10.1016/j.pnucene.2014.06.007
https://doi.org/10.1016/j.pnucene.2014.06.007
Publikováno v:
Annals of Nuclear Energy. 55:331-340
A steam generator tube rupture (SGTR) accident analysis for SMART was performed using the TASS/SMR-S code. SMART with a rated thermal power of 330 MWt has been developed at the Korea Atomic Energy Research Institute. The TASS/SMR-S code can analyze t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2197172d2eaec7f7f70ba1cd93dd97b1
https://doi.org/10.1016/j.anucene.2013.01.007
https://doi.org/10.1016/j.anucene.2013.01.007
Publikováno v:
Nuclear Engineering and Design. 238:1681-1689
Advanced integral-type pressurized water reactor with a maximum thermal power of 65 MW is under development at the Korea Atomic Energy Research Institute (KAERI). This 65 MW integral reactor incorporates a number of innovative design features. In the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::59a4adfc155f1100a6db003b9836b614
https://doi.org/10.1016/j.nucengdes.2007.12.008
https://doi.org/10.1016/j.nucengdes.2007.12.008
Publikováno v:
Nuclear Engineering and Design. 225:257-270
SMART is an integral type reactor of 330 MW, which enhances its safety by adopting inherent safety design features. Thermal hydraulic characteristics of transients in heat removal by a secondary system for the SMART have been carried out by means of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1908539b0a45d4aecb11dc8f1eef31aa
https://doi.org/10.1016/s0029-5493(03)00193-6
https://doi.org/10.1016/s0029-5493(03)00193-6
Autor:
Han Young Yoon, Jae Jun Jeong, Soo Hyoung Kim, Seung-Jun Lee, Ik Kyu Park, Jae Ryong Lee, Hyungrae Kim
Publikováno v:
Volume 2A: Thermal Hydraulics.
This paper presents a set of numerical procedure to innovate CFD code into a PWR component analysis code. A porous media approach is adapted to two-fluid model and conductor model, and a pack of constitutive relations close the numerical model into a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::74f84be0ec6f670190bb6b6c71ddb705
https://doi.org/10.1115/icone22-30098
https://doi.org/10.1115/icone22-30098
Publikováno v:
Nuclear Engineering and Design. 199:41-48
An experimental study has been performed to improve understanding of boiling phenomena and critical heat flux (CHF) in narrow gaps. The experiment has been performed with annular test sections submerged in a pool of saturated water under atmospheric
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f99c605c253c2a9227e3af97672cf2d0
https://doi.org/10.1016/s0029-5493(00)00250-8
https://doi.org/10.1016/s0029-5493(00)00250-8
Publikováno v:
International Communications in Heat and Mass Transfer. 27:285-292
In most CHF experiments, the CHF detection is usually accomplished by measurement of temperature using thermocouples, resistance temperature device(RTD), and etc. There is some ambiguity of human subjectivity in the experimental decision of CHF occur
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a653abca1a683ec218cfc1c3bf3c93a6
https://doi.org/10.1016/s0735-1933(00)00109-3
https://doi.org/10.1016/s0735-1933(00)00109-3
Publikováno v:
Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes.
CUPID-SG is a component scale thermal-hydraulic analysis tool based on CUPID, which is intended to be a computer code for analyzing two-phase flows in porous media with tube bundles such as PWR steam generators. CUPID-SG adopts two-fluid, three-field
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0777e1cf3b05519092f47f12bd82acc4
https://doi.org/10.1115/icone21-15124
https://doi.org/10.1115/icone21-15124