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| NO | Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date) |
|---|---|
Applicability of Swaging as an Alternative for the Fabrication of Accident-Tolerant Fuel Cladding Kim, Dae Yun; Lee, You Na; Kim, Joon Han; Kim, Yonghee; Yoon, Young Soo, ENERGIES, v.13, no.12, 2020-06 | |
| Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator Abdelhameed, Ahmed Amin E.; Chaudri, Khurrum Saleem; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.12, pp.2699 - 2708, 2020-12 | |
| Conceptual design of reactor system for hybrid micro modular reactor (H-MMR) using potassium heat pipe Choi, Young Jae; Lee, Seongmin; Jang, Seongdong; Son, In Woo; Kim, Yonghee; Lee, Jeong-Ik; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.370, 2020-12 | |
| Unstructured Mesh-Based Neutronics and Thermomechanics Coupled Steady-State Analysis on Advanced Three-Dimensional Fuel Elements with Monte Carlo Code iMC Kim, HyeonTae; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.195, no.5, pp.464 - 477, 2021-05 | |
| Polynomial relaxation in the quasi-static approach and its implementation in nonlinear reactor transient analyses Oh, Tae-suk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.158, 2021-08 | |
| A New Embedded Analysis with Pinwise Discontinuity Factors for Pin Power Reconstruction Yu, Hwanyeal; Jang, Seongdong; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.195, no.7, pp.766 - 777, 2021-07 | |
| Impacts of an ATF cladding on neutronic performances of the soluble-boron-free ATOM core Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.44, no.10, pp.8193 - 8207, 2020-08 | |
| Deterministic Truncation of the Monte Carlo Transport Solution for Reactor Eigenvalue and Pinwise Power Distribution Kim, Inhyung; Kim, HyeonTae; Kim, Yonghee, NUCLEAR SCIENCE AND ENGINEERING, v.194, no.1, pp.14 - 31, 2020-01 | |
| Physics study for high-performance and very-low-boron APR1400 core with 24-month cycle length Do, Manseok; Nguyen, Xuan Ha; Jang, Seongdong; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.5, pp.869 - 877, 2020-05 | |
| Potential of FAST (floating absorber for safety at transient) as a solution for positive coolant temperature coefficient in sodium-cooled FAST reactors Kim, Chihyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.137, 2020-03 |
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