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Showing results 6 to 12 of 12

Effect of oxide film on ECT detectability of surface IGSCC in laboratory-degraded alloy 600 steam generator tubing File

Lee, Tae Hyun , Ryu, Kyung Ha , Kim, Hong Deok , Hwang, Il Soon , Kim, Ji Hyun , Lee, Min Ho , Choi, Sungyeol

Article Issue Date2019-08 View13
Machine learning of LWR spent nuclear fuel assembly decay heat measurements File File

Ebiwonjumi, Bamidele , Cherezov, Alexey , Dzianisau, Siarhei , Lee, Deokjung

Article Issue Date2021-11 View11
The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation File File

Kim, Ji Yong , Lee, Yunju , Kim, Ji Hyun , Bang, In Cheol

Article Issue Date2023-09 View10
Uncertainties of PWR spent nuclear fuel isotope inventory for back-end cycle analysis with STREAM/RAST-K File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-08 View9
Uncertainty quanti fi cation of PWR spent fuel due to nuclear data and modeling parameters File File

Ebiwonjumi, Bamidele , Kong, Chidong , Zhang, Peng , Cherezov, Alexey , Lee, Deokjung

Article Issue Date2021-03 View7
Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K File File

Jang, Jaerim , Kong, Chidong , Ebiwonjumi, Bamidele , Cherezov, Alexey , Jo, Yunki , Lee, Deokjung

Article Issue Date2021-09 View15
Verification and validation of isotope inventory prediction for back-end cycle management using two-step method File File

Jang, Jaerim , Ebiwonjumi, Bamidele , Kim, Wonkyeong , Cherezov, Alexey , Park, Jinsu , Lee, Deokjung

Article Issue Date2021-07 View11
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