Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Yongdeok Lee"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 637-643 (2022)
Uranium and plutonium are required to be accounted in spent fuel head-end and major recovery area in pyro-process for safeguards purpose. The possibility of neutron resonance technique, as a non-destructive analysis, was simulated on isotopic fissile
Externí odkaz:
https://doaj.org/article/950156d41d7440e0b27b1204e7d9b61e
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 1, Pp 182-189 (2018)
A neutron generation system was developed to induce fissile fission in a lead slowing down spectrometer (LSDS) system. The source neutron is one of the key factors for LSDS system work. The LSDS was developed to quantify the isotopic contents of fiss
Externí odkaz:
https://doaj.org/article/4ebce90ad8a44252af81211bca351947
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 3, Pp 549-555 (2017)
A lead slowing-down spectrometer (LSDS) system is under development to analyze isotopic fissile content that is applicable to spent fuel and recycled material. The source neutron mechanism for efficient and effective generation was also determined. T
Externí odkaz:
https://doaj.org/article/d289f0aa86e541d5b24ab9cae8b9f28c
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 3, Pp 387-394 (2014)
A Slowing Down Time Spectrometer (SDTS) system is a highly efficient technique for isotopic nuclear material content analysis. SDTS technology has been used to analyze spent nuclear fuel and the pyro-processing of spent fuel. SDTS requires an externa
Externí odkaz:
https://doaj.org/article/a9d5adc0bcf84d7d82fa81c56fb3731d
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 7, Pp 921-928 (2013)
A future nuclear energy system is being developed at Korea Atomic Energy Research Institute (KAERI), the system involves a Sodium Fast Reactor (SFR) linked with the pyro-process. The pyro-process produces a source material to fabricate a SFR fuel rod
Externí odkaz:
https://doaj.org/article/0c827d14798946de8f53ddc9e9daaf38
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 637-643 (2022)
Uranium and plutonium are required to be accounted in spent fuel head-end and major recovery area in pyro-process for safeguards purpose. The possibility of neutron resonance technique, as a non-destructive analysis, was simulated on isotopic fissile
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::77333e3ac7b0e4e8a0aaa07d924678c2
http://www.sciencedirect.com/science/article/pii/S1738573321005052
http://www.sciencedirect.com/science/article/pii/S1738573321005052
Publikováno v:
Journal of the Korean Neurological Association. 38:281-285
Intraoperative neurophysiological monitoring (INM) is underutilized during the anteromesial temporal resection (AMTR) in epilepsy surgery. Herein we report a case with intraoperative capsular infarction which was early detected by INM. Among the moda
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::942cf7901742d92543f43efe9ab2cc35
https://doi.org/10.17340/jkna.2020.4.5
https://doi.org/10.17340/jkna.2020.4.5
Autor:
Seong-Kyu Ahn, YongDeok Lee
Publikováno v:
Annals of Nuclear Energy. 132:82-86
Isotopic fissile content assay was performed in a designed lead slowing down spectrometer (LSDS) system. In the system, the fission measurement was performed for 11 – 20 wt% of Pu239 with 1 wt% of Pu241 and U235. The self-shielding factor was appli
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be82497d1dadf5b218354501f092c237
https://doi.org/10.1016/j.anucene.2019.03.046
https://doi.org/10.1016/j.anucene.2019.03.046
Publikováno v:
Annals of Nuclear Energy. 88:24-29
This study illustrates the implementation of the newly suggested layer-splitting testing technique. This technique is introduced in order to be implemented in examining suggested formalisms for the recursive scheme (or iterative scheme). The recursiv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ab82e398be19eee13105d0c616cec74f
https://doi.org/10.1016/j.anucene.2015.10.032
https://doi.org/10.1016/j.anucene.2015.10.032
End effect analysis with various axial burnup distributions in high density spent fuel storage racks
Publikováno v:
Annals of Nuclear Energy. 81:174-178
End effect of spent fuel comes from the difference between uniform and actual axial burnup distributions of fuel assemblies. It is significant to control the criticality safety in spent fuel storage and transportation. This work is focused on estimat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::319243b57151d8f67eff09669cebbeb6
https://doi.org/10.1016/j.anucene.2015.01.042
https://doi.org/10.1016/j.anucene.2015.01.042