| 669158 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX |
2021-03-25 |
10.1016/j.net.2020.08.001 |
Xiao, Bowen, Wei, Linfang, Zheng, Youqi, Zhang, Bin, Wu, Hongchun |
| 669157 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT |
2021-03-25 |
10.1016/j.net.2020.07.043 |
Zhao, Xiaohan, Wang, Mingjun, Wu, Ge, Zhang, Jing, Tian, Wenxi, Qiu, Suizheng, Su, G.H. |
| 669156 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform |
2021-03-25 |
10.1016/j.net.2020.08.006 |
Kim, Kyung Mo, Bang, In Cheol |
| 669155 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Sorption of Pd on illite, MX-80 bentonite and shale in Na-Ca-Cl solutions |
2021-03-25 |
10.1016/j.net.2020.09.001 |
Goguen, Jared, Walker, Andrew, Racette, Joshua, Riddoch, Justin, Nagasaki, Shinya |
| 669154 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Measuring thermal conductivity and water suction for variably saturated bentonite |
2021-03-25 |
10.1016/j.net.2020.08.017 |
Yoon, Seok, Kim, Geon-Young |
| 669153 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method |
2021-03-25 |
10.1016/j.net.2020.07.033 |
Lee, Eun-ki |
| 669152 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Establishment of the design stress intensity value for the plate-type fuel assembly using a tensile test |
2021-03-25 |
10.1016/j.net.2020.07.038 |
Kim, Hyun-Jung, Tahk, Young-Wook, Jun, Hyunwoo, Kong, Eui-Hyun, Oh, Jae-Yong, Yim, Jeong-Sik |
| 669151 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt |
2021-03-25 |
10.1016/j.net.2020.07.042 |
Ezell, N. Dianne Bull, Raiman, Stephen S., Kurley, J. Matt, McDuffee, Joel |
| 669150 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media |
2021-03-25 |
10.1016/j.net.2020.08.004 |
Rafique, Mohsin, Khan, Atika, Afzal, Naveed, Farooq, Ameeq, Imran, M. |
| 669149 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Fracture simulation of SFR metallic fuel pin using finite element damage analysis method |
2021-03-25 |
10.1016/j.net.2020.08.009 |
Jung, Hyun-Woo, Song, Hyun-Kyu, Kim, Yun-Jae, Jerng, Dong-Wook |
