| 1 | A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters Kim, Yonghee; Hartanto, Donny; Kim, Woosong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.642 - 649, 2016-06 |
| 2 | A monte carlo method for solving heat conduction problems with complicated geometry Shentu, Jun; Yun, Sung-Hwan; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.39, pp.207 - 214, 2007-06 |
| 3 | 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 |
| 4 | A study of influence of the initial source distribution on convergence of multiplication factor (keff) in monte carlo calculation = 몬테카를로 계산에서 초기 중성자 분포가 유효증배계수의 수렴에 미치는 영향에 관한 연구link Abi Muttaqin Bin Jalal Bayar; Bayar; et al, 한국과학기술원, 2013 |
| 5 | (A) new approach to solving heat conduction problems with complicated geometry based on a monte carlo method = 몬테칼로 방법에 기반한 복잡한 구조를 갖는 열전달 문제의 해를 위한 새로운 접근link Shentu, Jun; 신도군; et al, 한국과학기술원, 2007 |
| 6 | (A) physics and conceptual study on LEU-loaded nuclear thermal propulsion reactors = 저농축우라늄 연료 기반 우주로켓 추진용 원자로에 대한 물리적 개념연구link Venneri, Paolo Frnacesco; Kim, Yonghee; et al, 한국과학기술원, 2017 |
| 7 | Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method Yun, Sung-Hwan; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.37, no.12, pp.1649 - 1658, 2010-12 |
| 8 | AN IMPROVED MONTE CARLO METHOD APPLIED TO THE HEAT CONDUCTION ANALYSIS OF A PEBBLE WITH DISPERSED FUEL PARTICLES Song, Jae Hoon; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.3, pp.279 - 286, 2009-04 |
| 9 | Angle dependent focal spot size of a conical X-ray target Raza, Hamid Saeed; Kim, Hyun Jin; Kim, Hyun Nam; Cho, Sung-Oh, APPLIED RADIATION AND ISOTOPES, v.96, pp.6 - 12, 2015-02 |
| 10 | Application of Monte Carlo method with forward and adjoint midway coupling to radiation transport calculation = Forward와 adjoint 중간지점 결합에 의한 몬테칼로방법의 방사선 수송계산에서의 응용link Ryu, Ho-Kyu; 유호규; et al, 한국과학기술원, 1999 |
| 11 | Attenuation Curves of Neutrons from 400 to 550 Mev/u for Ca, Kr, Sn, and U ions in Concrete on a Graphite Target for the Design of Shielding for the RAON In-flight Fragment Facility in Korea Lee, Eunjoong; Kim, Junhyeok; Kim, Giyoon; KIM, Jinhwan; Park, Kyungjin; Cho, Gyuseong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.275 - 283, 2019-02 |
| 12 | Behavior of characteristic X-rays from a partial-transmission-type X-ray target Raza, Hamid Saeed; Kim, Hyun Jin; Ha, Jun Mok; Cho, Sung Oh, APPLIED RADIATION AND ISOTOPES, v.80, pp.67 - 72, 2013-10 |
| 13 | Comparison of stochastic models in Monte Carlo simulation of coated particle fuels Yu, Hui; Cho, Nam-Zin, QIANGJIGUANG YU LIZISHU/HIGH POWER LASER AND PARTICLE BEAMS, v.25, no.1, pp.143 - 146, 2013-01 |
| 14 | Depletion analysis of a solid-type blanket design for ITER Yun, Sung-Hwan; Cho, Nam-Zin; Ahn, Mu-Young; Cho, Seung-Yon, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1654 - 1660, 2008-12 |
| 15 | Fission and Surface Source Iteration Method for Domain Decomposed Monte Carlo Whole-Core Calculation Jo, Yugwon; Cho, Nam Zin, NUCLEAR SCIENCE AND ENGINEERING, v.182, no.2, pp.181 - 196, 2016-02 |
| 16 | Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor Yun, Sung-Hwan; Cho, Nam-Zin; Ahn, Mu-Young; Cho, Seung-Yon, FUSION ENGINEERING AND DESIGN, v.85, no.10-12, pp.2222 - 2226, 2010-12 |
| 17 | Improvement of CANDU safety parameters by using CANFLEX = CANFLEX를 이용한 CANDU노심의 안전인자 향상 연구link Kim, Woo-Song; 김우송; et al, 한국과학기술원, 2013 |
| 18 | Improvement of CANDU safety parameters by using the CANFLEX fuel Kim, Woosong; Motalab, Mohammad Abdul; Bae, Jun Ho; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.94, pp.793 - 801, 2016-08 |
| 19 | Inline critical boron concentration search with p-CMFD feedback in whole-core continuous-energy Monte Carlo simulation Jo, Yugwon; Cho, Nam Zin, ANNALS OF NUCLEAR ENERGY, v.120, pp.402 - 409, 2018-10 |
| 20 | Monte carlo analysis on the operational characteristics of a carbon-nanotube-based miniature X-ray tube = 탄소나노튜브 기반 초소형 X-선 튜브의 동작특성에 관한 몬테카를로 분석link Raza, Hamid Saeed; RAZA; et al, 한국과학기술원, 2015 |
| 21 | MONTE CARLO METHOD EXTENDED TO HEAT TRANSFER PROBLEMS WITH NON-CONSTANT TEMPERATURE AND CONVECTION BOUNDARY CONDITIONS Cho, Bum Hee; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.42, no.1, pp.65 - 72, 2010-02 |
| 22 | A Monte Carlo Method of Solving Heat Conduction Problems with Complicated Geometry Jun, Shentu; Yun, Sunghwan; Cho, Nam Zin, Nuclear Engineering and Technology, Vol.39, No.3, pp.207-214, 2007-06 |
| 23 | Neutronic analysis of the KSTAR tokamak using beowulf cluster Park, JH; Cho, Nam-Zin; Kim, J, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.37, no.1, pp.276 - 279, 2000 |
| 24 | New monte carlo based time-domain noise analysis and its application to a design of low-noise CMOS readout circuits = 새로운 몬테카를로 방법을 이용한 시간영역 잡음 해석과 이를 이용한 저잡음 CMOS Readout 회로 설계에 관한 연구link Lee, Tae-Hoon; 이태훈; et al, 한국과학기술원, 2003 |
| 25 | Nuclear-thermal analysis of a unit fuel element in HTGRs based on two-temperature homogenized model = 두 온도 균질화법에 의한 고온가스로 핵연료요소체의 핵열해석link Yu, Hui; 유휘; et al, 한국과학기술원, 2010 |
| 26 | Reactor condition monitoring and singularity detection via wavelet and use of entropy in monte carlo calculation = 웨이브렛을 통한 원자로 상태 감시와 특이점 감지 및 몬테칼로 계산에서의 엔트로피 이용link Kim, Ok-Joo; 김옥주; et al, 한국과학기술원, 2007 |
| 27 | 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 |
| 28 | Semi-analog monte carlo (SMC) method for time-dependent non-linear three-dimensional heterogeneous radiative transfer problems = 시간 의존적 비선형 3차원 비균질 복사전달 문제를 위한 SMC 방법론link Yun, Sung-Hwan; 윤성환; et al, 한국과학기술원, 2004 |
| 29 | STUDY OF CORE SUPPORT BARREL VIBRATION MONITORING USING EX-CORE NEUTRON NOISE ANALYSIS AND FUZZY LOGIC ALGORITHM Christian, Robby; Song, Seon Ho; Kang, Hyun-Gook, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.2, pp.165 - 175, 2015-03 |
| 30 | 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 |
| 31 | Whole-core depletion calculation using domain decomposed continuous-energy Monte Carlo simulation via McBOX with p-CMFD acceleration and inline feedback Jo, YuGwon; Kim, HyeonTae; Kim, Yonghee; Cho, Nam Zin, ANNALS OF NUCLEAR ENERGY, v.139, 2020-05 |
