| 693348 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Enhancing utilization and ensuring security: Insights to compromise contradicting conditions in new research reactors |
2021-05-25 |
10.1016/j.net.2020.11.010 |
Alrammah, Ibrahim |
| 693347 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Influence and analysis of a commercial ZigBee module induced by gamma rays |
2021-05-25 |
10.1016/j.net.2020.11.017 |
Shin, Dongseong, Kim, Chang-Hwoi, Park, Pangun, Kwon, Inyong |
| 693346 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Illustration of Nagra's AMAC approach to Kori-1 NPP decommissioning based on experience from its detailed application to Swiss NPPs |
2021-05-25 |
10.1016/j.net.2020.10.010 |
Volmert, Ben, Bykov, Valentyn, Petrovic, Dorde, Kickhofel, John, Amosova, Natalia, Kim, Jong Hyun, Cho, Cheon Whee |
| 693345 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Thermal behavior of groundwater-saturated Korean buffer under the elevated temperature conditions: In-situ synchrotron X-ray powder diffraction study for the montmorillonite in Korean bentonite |
2021-05-25 |
10.1016/j.net.2020.10.012 |
Park, Tae-Jin, Seoung, Donghoon |
| 693344 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Evaluation of decontamination factor of radioactive methyl iodide on activated carbons at high humid conditions |
2021-05-25 |
10.1016/j.net.2020.10.020 |
Choi, Byung-Seon, Kim, Seon-Byeong, Moon, Jeikwon, Seo, Bum-Kyung |
| 693343 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Structural stability analysis of waste packages containing low- and intermediate-level radioactive waste in a silo-type repository |
2021-05-25 |
10.1016/j.net.2020.10.019 |
Byeon, Hyeongjin, Jeong, Gwan Yoon, Park, Jaeyeong |
| 693342 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Dissolution behavior of SrO into molten LiCl for heat reduction in used nuclear fuel |
2021-05-25 |
10.1016/j.net.2020.11.019 |
Kang, Dokyu, Amphlett, James T.M., Choi, Eun-Young, Bae, Sang-Eun, Choi, Sungyeol |
| 693341 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Thermal-fluid-structure coupling analysis for plate-type fuel assembly under irradiation. Part-I numerical methodology |
2021-05-25 |
10.1016/j.net.2020.10.016 |
Li, Yuanming, Yuan, Pan, Ren, Quan-yao, Su, Guanghui, Yu, Hongxing, Wang, Haoyu, Zheng, Meiyin, Wu, Yingwei, Ding, Shurong |
| 693340 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Thermal-fluid-structure coupling analysis on plate-type fuel assembly under irradiation. Part-II Mechanical deformation and thermal-hydraulic characteristics |
2021-05-25 |
10.1016/j.net.2020.11.031 |
Li, Yuanming, Ren, Quan-yao, Yuan, Pan, Su, Guanghui, Yu, Hongxing, Zheng, Meiyin, Wang, Haoyu, Wu, Yingwei, Ding, Shurong |
| 693339 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Mesocarbon microbead densified matrix graphite A3-3 for fuel elements in molten salt reactors |
2021-05-25 |
10.1016/j.net.2020.10.018 |
Wang, Haoran, Xu, Liujun, Zhong, Yajuan, Li, Xiaoyun, Tang, Hui, Zhang, Feng, Yang, Xu, Lin, Jun, Zhu, Zhiyong, You, Yan, Lu, Junqiang, Zhu, Libing |
