Zobrazeno 1 - 10
of 29
pro vyhledávání: '"Ju-chan Lee"'
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 6, Pp 1878-1886 (2021)
For industrial package (IP)-type transport containers for radioactive materials, a free drop test should be conducted under regulatory conditions. Owing to various uncertainties observed during the drop test, errors in drop angles inevitably occur. I
Externí odkaz:
https://doaj.org/article/f73203b53f2c41268306c761f9fa8d22
Publikováno v:
Journal of the Korean Society for Environmental Technology. 22:480-487
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::386ee5575f0ab2011c0c402a9c41f664
https://doi.org/10.26511/jkset.22.6.11
https://doi.org/10.26511/jkset.22.6.11
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 6, Pp 1878-1886 (2021)
For industrial package (IP)-type transport containers for radioactive materials, a free drop test should be conducted under regulatory conditions. Owing to various uncertainties observed during the drop test, errors in drop angles inevitably occur. I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7f1ec0d3acc8b2460bc7855e2696ffd3
https://doi.org/10.1016/j.net.2020.12.022
https://doi.org/10.1016/j.net.2020.12.022
Autor:
Ju-Chan Lee, Dong Il Park, Hyeon-Uk Seo, Hyun Min Do, Mok HyungSoo, Ju-Suk Lee, Choi， Tae-Yong
Publikováno v:
Journal of Institute of Control, Robotics and Systems. 26:1067-1075
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7446b70c9e7af96c59bdd2b408597db3
https://doi.org/10.5302/j.icros.2020.20.0160
https://doi.org/10.5302/j.icros.2020.20.0160
Autor:
Ju-Chan Lee, Mok HyungSoo, Byoung-Sun Ahn, Hong-Woo Yoon, Seung-Hun Lee, Sang-Uk Park, Jaeyoung Park
Publikováno v:
The transactions of The Korean Institute of Electrical Engineers. 69:37-41
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44f3b3059d9096c1234cb6a144e6d3af
https://doi.org/10.5370/kiee.2020.69.1.37
https://doi.org/10.5370/kiee.2020.69.1.37
Publikováno v:
Nuclear Engineering and Design. 338:158-165
KORAD-B/II shipping packages, developed by the Korea Radioactive Waste Agency (KORAD), are used to transport C4 concrete packages, which are temporarily stored in the HANUL nuclear power plant. These packages must therefore meet the requirements of t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::69bc60ccc1d54b2c797546a66b81ace4
https://doi.org/10.1016/j.nucengdes.2018.08.007
https://doi.org/10.1016/j.nucengdes.2018.08.007
Publikováno v:
Annals of Nuclear Energy. 120:715-722
The flow characteristics inside a fuel basket containing a spent nuclear fuel assembly were analyzed in this study. The geometry of a nuclear fuel assembly is very complicated; hence, a porous media model and an effective thermal conductivity were us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::182f027719f486fbf7aeac4c2480590f
https://doi.org/10.1016/j.anucene.2018.06.027
https://doi.org/10.1016/j.anucene.2018.06.027
Publikováno v:
Journal of the Nuclear Fuel Cycle and Waste Technology(JNFCWT). 16:223-232
사용후핵연료 저장용기의 공기 흡입구 및 배기구에는 외부환경으로부터 이물질의 유입을 방지하기 위하여 bird screen이 설치되며, bird screen에서는 공기의 유동 저항이 발생하게 된다. 본 연
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e50f201091d998ddccc7e863ccce973
https://doi.org/10.7733/jnfcwt.2018.16.2.223
https://doi.org/10.7733/jnfcwt.2018.16.2.223
Publikováno v:
Annals of Nuclear Energy. 112:322-327
Spent nuclear fuel generated at nuclear power plants must be safely stored during interim storage periods. A concrete storage cask developed for this purpose should be able to adequately emit the decay heat from the spent nuclear fuel; it should also
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b18ae6242cb7ecbdd08e385d2bcad9a
https://doi.org/10.1016/j.anucene.2017.10.005
https://doi.org/10.1016/j.anucene.2017.10.005
Publikováno v:
Annals of Nuclear Energy. 149:107791
The weight of spent nuclear fuel concrete storage casks usually exceeds 100 tons. Therefore, thermal testing of prototype casks is expensive and time consuming. In this study, thermal testing method using a scaled-down model of a storage cask was dev
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a8b7601ba54aebd6b38cb99919389cdf
https://doi.org/10.1016/j.anucene.2020.107791
https://doi.org/10.1016/j.anucene.2020.107791