• Title/Summary/Keyword: 열수력

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Thermal-Hydraulic Research Review and Cooperation Outcome for Light Water Reactor Fuel (경수로핵연료 열수력 연구개발 분석 및 연산학 협력 성과)

  • In, Wang Kee;Shin, Chang Hwan;Lee, Chi Young;Lee, Chan;Chun, Tae Hyun;Oh, Dong Seok
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.40 no.12
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    • pp.815-824
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    • 2016

  • The fuel assembly for pressurized water reactor (PWR) consists of fuel rod bundle, spacer grid and bottom/top end fittings. The cooling water in high pressure and temperature is introduced in lower plenum of reactor core and directed to upper plenum through the subchannel which is formed between the fuel rods. The main thermal-hydraulic performance parameters for the PWR fuel are pressure drop and critical heat flux in normal operating condition, and quenching time in accident condition. The Korea Atomic Energy Research Institute (KAERI) has been developing an advanced PWR fuel, dual-cooled annular fuel and accident tolerant fuel for the enhancement of fuel performance and the localization. For the key thermal-hydraulic technology development of PWR fuel, the KAERI LWR fuel team has conducted the experiments for pressure drop, turbulent flow mixing and heat transfer, critical heat flux(CHF) and quenching. The computational fluid dynamics (CFD) analysis was also performed to predict flow and heat transfer in fuel assembly including the spent fuel assembly in dry cask for interim repository. In addition, the research cooperation with university and nuclear fuel company was also carried out to develop a basic thermal-hydraulic technology and the commercialization.

  • https://doi.org/10.3795/KSME-B.2016.40.12.815 인용 PDF KSCI

Development of Backup Calculation System for a Nuclear Steam Supply System Thermal-Hydraulic Model ARTS (Advanced Real-time Thermal Hydraulic Simulation) of the W/H Type NPP (W/H형 원전 시뮬레이터용 핵 증기공급 계통 열수력모델 ARTS(Advanced Real-time Thermal Hydraulic Simulation)의 보조계산체계 개발)

  • 서재승;전규동
    • Journal of Energy Engineering
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    • v.13 no.1
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    • pp.51-59
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    • 2004

  • The NSSS (Nuclear Steam Supply System) thermal-hydraulic programs adopted in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited compulsational capability at that time, they usually used very simplified physical models for a real-time simulation of NSSS thermal-hydraulic transients, which entails inaccurate results and, thus, the possibility of so-called "negative training", especially for complicated two-phase flows in the reactor coolant system. In resolve the problem, KEPRI developed a realistic NSSS T/H program ARTS which was based on the RETRAN-3D code for the improvement of the Nuclear Power Plant full-scope simulator. The ARTS (based on the RETRAN-3D code) guarantees the real-time calculations of almost all transients and ensures the robustness of simulations. However, there is some possibility of failing to calculate in the case of large break loss of coolant accident (LBLOCA) and low-pressure low-flow transient. In this case, the backup calculation system cover automatically the ARTS. The backup calculation system was expected to provide substantially more accurate predictions in the analysis of the system transients involving LBLOCA. The results were reasonable in terms of accuracy, real-time simulation, robustness and education of operators, complying with FSAR and the AMSI/ANS-3.5-1998 simulator software performance criteria.

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The Semi-Implicit Numerical Scheme for Transient Two-Phase Flows on Unstructured Grids (과도 다차원 2상 유동 해석을 위한 비정렬 격자계에서의 Semi-Implicit 수치 해법 개발)

  • Cho, H.K.;Park, I.K.;Yoon, H.Y.;Kim, J.;Jeong, J.J.
    • Journal of Energy Engineering
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    • v.17 no.4
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    • pp.218-226
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    • 2008

  • A component-scale two-phase analysis code has been developed for a realistic simulation of two-phase flow transients in a light water nuclear reactor component. In the code, a two-fluid three-field model is adopted and the governing equations are solved on an unstructured mesh. For the numerical solution scheme, the semi-implicit method used in the RELAP5 code was selected, which has been proved to be very stable and accurate for most of practical applications. However, some modifications were needed for its application to an unstructured non-staggered grid. This paper presents the modified semi-implicit numerical method for unstructured grid and the preliminary results of the calculations.

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