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Kim, Yonghee (김용희)
교수, (원자력및양자공학과)

http://rptl.kaist.ac.kr

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    NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
    1
    Evaluation of effective kinetic parameters and adjoint flux distribution using iterated fission probability in the iMC Monte Carlo code

    Oh, Taesuk; Kim, Inyup; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.210, 2025-01

    2
    Load-Follow Operation in LEU plus loaded very-low soluble boron APR1400

    Khalefih, Husam; Kim, Yonghee, PROGRESS IN NUCLEAR ENERGY, v.177, 2024-12

    3
    A study on the applicability of simplified few-group GET (Generalized Equivalence Theory) to cylindrical molten salt fast reactor

    Hong, Sungtaek; Oh, Taesuk; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.10, pp.4207 - 4218, 2024-10

    4
    Development of an on-demand flooding safety system achieving long-term inexhaustible cooling of small modular reactors employing metal containment vessel

    Park, Jae Hyung; Im, Jihun; An, Hyo Jun; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.7, pp.2534 - 2544, 2024-07

    5
    An embedded coupling design and development of NECP-Bamboo2.0 and START for PWR whole-core pin-by-pin analysis

    Wang, Sicheng; Kim, Yonghee; Li, Yunzhao; et al, ANNALS OF NUCLEAR ENERGY, v.199, 2024-05

    6
    Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor

    An, Hyo Jun; Park, Jae Hyung; Song, Chang Hyun; et al, Nuclear Engineering and Technology, v.56, no.3, pp.949 - 958, 2024-03

    7
    Burnable Absorber Design Study for a Passively-Cooled Molten Salt Fast Reactor

    Aufanni, Nariratri Nur; Lee, Eunhyug; Oh, Taesuk; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.900 - 906, 2024-03

    8
    Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor

    Choi, Won Jun; Park, Jae Hyung; Lee, Juhyeong; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.1002 - 1012, 2024-03

    9
    Multi-batch core design study for innovative small modular reactor based on centrally-shielded burnable absorber

    Wijaya, Steven; Nguyen, Xuan Ha; Jeong, Yunseok; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.907 - 915, 2024-03

    10
    Supercritical CO2-cooled fast reactor and cold shutdown system for ship propulsion

    Ju, Kwangho; Ryu, Jaehyun; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.1022 - 1028, 2024-03

    11
    Real variance estimation in iDTMC-based depletion analysis

    Kim, Inyup; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.11, pp.4228 - 4237, 2023-11

    12
    Daily Load-Follow Operation in LEU plus -Loaded APR1400 Using Mode-K plus Control Logic

    Khalefih, Husam; Jeong, Yunseok; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.2023, 2023-10

    13
    LEU plus loaded APR1400 using accident tolerant fuel cladding for 24-month two-batch fuel management scheme

    Khalefih, Husam; Oh, Taesuk; Jeong, Yunseok; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.7, pp.2578 - 2590, 2023-07

    14
    Development and validation of multiphysics PWR core simulator KANT

    Oh, Taesuk; Jeong, Yunseok; Khale, Husam; et al, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.6, pp.2230 - 2245, 2023-06

    15
    A leakage correction with burnup-dependent GPS method in two-step core depletion analysis

    Jeong, Hae Sun; Oh, Taesuk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.183, 2023-04

    16
    A new approach for uncertainty quantification in predictor-corrector quasi-static Monte Carlo transient simulation

    Oh, Taesuk; Kim, Inyup; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.11, 2023-01

    17
    Possible power increase in a natural circulation Soluble-Boron-Free Small Modular Reactor using the Truly Optimized PWR lattice

    Wijaya, Steven; Nguyen, Xuan Ha; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.1, pp.330 - 338, 2023-01

    18
    A study of the behavior of the floating absorber for safety at transient(FAST) in an innovative sodium-cooled fast reactor (iSFR)

    Lee, Seongmin; Kim, Yonghee; Choi, Yonadan; et al, ANNALS OF NUCLEAR ENERGY, v.179, 2022-12

    19
    Analysis on short-term decay heat after shutdown during load-follow operation with seasonal and daily scenarios

    Hwang, Dae Hee; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.54, no.10, pp.3878 - 3887, 2022-10

    20
    Improved macroscopic depletion in 2-D nodal analysis by 2x2 albedo-corrected parameterized equivalence constants method

    Jang, Seongdong; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.175, 2022-09
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