Deokjung Lee
UNIST Energy Engineering · 공학
이 교수의 연구실은 원자로 물리 및 해석 기법의 정밀도 향상을 위한 핵심 소프트웨어 개발과 검증에 중점을 두고 있습니다. 특히 PWR 및 MSBR 등 다양한 Reactor 설계를 위한 고정밀 수치 해석 코드(예: STREAM, RAST-K 2.0)의 개발과 V&V, 레이저-기반 자기屏蔽 효과 분석, 연소계산 정밀도 향상 기법 등에 대한 연구를 수행하고 있습니다. 또한, 감도 분석, 연소계산의 수렴성 향상, 고차원적 반응성 계산 기법 등 핵심 핵심 기술을 다루며, 실제 원자로 설계에 응용 가능한 정확한 해석 기법을 지속적으로 개발하고 있습니다.
표시된 성과는 수집된 데이터 기준으로 산출되며, 일부 차이가 있을 수 있습니다.
This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for a pressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion code RAST-K 2.0 have been developed by a computational reactor physics and experiment laboratory (CORE) of Ulsan National Institute of Science and Technology (UNIST) for an accurate two-step PWR analysis. The calculation modules of each code were already verified against various benchmark problem
The simulation of whole core depletion and continuous reprocessing of a molten salt breeder reactor (MSBR) was performed. The MSBR model was built using MCNP6, and the depletion and reprocessing simulations were modeled using CINDER90 and a Python script. The Python script was introduced to implement online reprocessing of molten salt fuel and the feeding of new fertile material with 3-day depletion intervals during the simulations. The simulation started with the reference composition from the
This paper reports on the development and verification of three new resonance self-shielding methods. The verifications were performed using the new neutron transport code, STREAM. The new methodologies encompass the extension of energy range for resonance treatment, the development of optimum rational approximation, and the application of resonance treatment to isotopes in the cladding region. (1) The extended resonance energy range treatment has been developed to treat the resonances below 4 e
A new calculational model of detector sensitivity, which is defined as the ratio of electric current to neutron flux, for self-powered neutron detector (SPND) is presented in this paper. Since Warren developed a sensitivity calculation model based on a multi-step analytic approach in 1972, there have been a lot of researches aimed at improving the accuracy of his model by partially employing Monte Carlo (MC) simulations in some of the calculation steps. However, there still exist assumptions suc
The huge absorption cross sections of 155Gd and 157Gd cause strong spatial shielding effects in Gd-bearing pins. A high-order depletion method has been developed for CASMO-5 to address the issue of the small depletion steps typically required for Gd-bearing fuel assemblies. In this method, the microscopic absorption reaction rates of gadolinium isotopes are assumed to be quadratic functions of the number density of 155Gd rather than the constant reaction rate assumption in the conventional predi