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Browsing by Author : Kim, Mi Jin

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Absorber Contents and Wall Thickness of Efficient Used Nuclear Fuel Storage

Sohn, Dong-Seong , Kim, Mi Jin , Lee, Hee-Jae

Conference Paper Issue Date2015-09-21 View84
CFD Analysis of Dry Spent Fuel Storage with Advanced Neutron Absorber under Normal Condition

Lee, Hee Jae , Kim, Mi Jin , Jeong, Gwan Yoon , Cho, Tae Won , Lee, Cheol Min , Kim, Ji-Hyeon , Sohn, Dong-Seong

Conference Paper Issue Date2016-08-03 View82
Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials File

Kim, Mi Jin , Kim, Wonkyeong , Lee, Deokjung , Lemaire, Matthieu , Lee, Hee-Jae , Sohn, Dong-Seong , Kwon, Hyukjoo

Article Issue Date2019-08 View122
Gd and B Based Integral Neutron Absorber for Spent Fuel Transportation and Storage System File

Kim, Mi Jin

Thesis Issue Date2020-02 View65
High temperature oxidation of the Zr-1Nb-1Sn-0.1Fe cladding tube at the temperatures of 1000 - 1200°C

Lee, Cheolmin , Cho, Taewon , Jeonga, Gwan Yoon , Kim, Mi Jin , Kim, Jihyeon , Lee, Heejae , Mok,Yongkyoon , Sohn, Dong-Seong

Conference Paper Issue Date2016-04-17 View92
Photoneutron production in heavy water reactor fuel lattice from accelerator-driven bremsstrahlung File

Fynan, Douglas A. , Seo, Yeseul , Kim, Gitae , Barros, Silvia , Kim, Mi Jin

Article Issue Date2021-06 View128
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