CORE (COmputational and Reactor physics and Experiment)

CORE (COmputational and Reactor physics and Experiment)

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CORE (COmputational and Reactor physics and Experiment)

UNIST CORE (COmputational Reactor physics and Experiment laboratory) is an academic laboratory dedicated to the research in nuclear reactor physics. The laboratory actively develops theoretical methods and computer codes to tackle neutron transport and diffusion theory in all its aspects: collision with medium, slowing-down, scattering, absorption, nuclear fission, chain reaction, secondary particle production and nuclide transmutation. The laboratory manages the knowledge required for reactor core design, analysis and operation and conducts studies in the fields of criticality, reactivity feedback and reactivity control, reactor kinetics, nuclear fuel depletion, perturbation theory, deep-penetration shielding, steady-state and transient simulations, reactor design and safety analysis, and many more.

Major research field

Reactor Physics, Numerical Methods for Transport and Diffusion Analysis, Advanced Reactor Designs and Analysis, High Performance Computing, Lattice Ph

Desired field of research

MOC transport code, 3D Nodal diffusion code, Monte Carlo code, Reactor design, Fast reactor analysis, Multi-physics coupling, Sensitivity & uncertainty analysis, AI & simulator

Research Keywords and Topics

Reactor physics, code development, method development, advanced reactor design, high-performance computing, reactor core simulator, SMR(Small Modular Reactor) design

Research Publications
MORE

1. COMPUTER PHYSICS COMMUNICATIONS / Three-dimensional method of characteristics/diamond-difference transport analysis method in STREAM for whole-core neutron transport calculation / Choi, Sooyoung, Lee, Deokjung / 2021-03
2. ANNALS OF NUCLEAR ENERGY / MCS – A Monte Carlo particle transport code for large-scale power reactor analysis / Lee, Hyunsuk; Kim, Wonkyeong; Zhang, Peng; Lemaire, Matthieu; Khassenov, Azamat; Yu, Jiankai; Jo, Yunki; Park, Jinsu; Lee, Deokjung / 2020-05
3. NUCLEAR ENGINEERING AND TECHNOLOGY / Verification and validation of STREAM/RAST-K for PWR analysis / Choe, Jiwon; Choi, Sooyoung; Zhang, Peng; Park, Jinsu; Kim, Wonkyeong; Shin, Ho Cheol; Lee, Hwan Soo; Jung, Ji-Eun; Lee, Deokjung / 2019-04
4. JOURNAL OF COMPUTATIONAL PHYSICS / Resonance treatment using pin-based pointwise energy slowing-down method / Choi, Sooyoung; Lee, Changho; Lee, Deokjung / 2017-02

Patents

1. [USA] FUEL ASSEMBLY DESIGN CONCEPT AND MIXED CYCLE SENGTH OPERATION METHOD FOR LONG CYCLE LENGTH PRESSURIZED WATER REACTOR OPERATION / Deokjung Lee, Eun Jeong, Sooyoung Choi, Jinsu Park, Jaerim Jang, Peng Zhang / 2022
2. [KOR] HYBRID DEPLETION METHOD FOR LIGHT WATER REACTOR ANALYSIS / Deokjung Lee, Wonkyeong Kim, Sooyoung Choi, Hyunsuk Lee / 2017
3. [KOR] APPARATUS AND METHOD FOR REACTOR CORE ANALYSIS USING PSM / Deokjung Lee, Sooyoung Choi / 2017

국가과학기술표준분류

  • EG. 원자력
  • EG01. 원자로노심기술
  • EG0102. 노심 핵설계 기술

국가기술지도분류

  • 환경/에너지 프론티어 진흥
  • 031700. 미래형/일체형원자로기술

녹색기술분류

  • 녹색기술관련 과제 아님
  • 녹색기술관련 과제 아님
  • 999. 녹색기술 관련과제 아님

6T분류

  • 기타 분야
  • 기타 분야
  • 070000. 위의 미래유망신기술(6T) 103개 세분류에 속하지 않는 기타 연구