• Title/Summary/Keyword: MARS 코드

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COMPONENT AND SYSTEM MULTI-SCALE DIRECT-COUPLED CODE IMPLEMENTATION USING CUPID AND MARS CODES (CUPID 코드와 MARS 코드를 이용한 기기/계통 다중스케일 연계 해석 코드 구현)

  • Park, I.K.
    • Journal of computational fluids engineering
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    • v.21 no.3
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    • pp.89-97
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    • 2016

  • In this study, direct code coupling, in which two codes share a single flow field, was conducted using 3-dimensional high resolution thermal hydraulics code, CUPID and 1-dimensional system analysis code, MARS. This approach provide the merit to use versatile capability of MARS for nuclear power plants and 3-dimensional T/H analysis capability of CUPID. Numerical Method to directly couple CUPID and MARS was described in this paper. The straight flow and manometer flow oscillation were calculated to verify conservation of coupled CUPID/MARS code in mass, momentum, and energy. This verification calculations indicates that the CUPID/MARS is coupled appropriately in numerical aspect and the coupled code can be applied to nuclear reactor thermal hydraulics after validation against integral transient experiments.

  • https://doi.org/10.6112/kscfe.2016.21.3.089 인용 PDF KSCI

MARS Code Applicability Assessments for the HTGR RCCS (고온가스로 원자로공동냉각계통(RCCS)에 대한 MARS Code 적용성 평가)

  • Kang Doo-Hyuk;Kim Hyung-Seok;Chung Bum-Jin
    • Journal of Energy Engineering
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    • v.14 no.4 s.44
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    • pp.232-240
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    • 2005

  • In this study, the IAEA Benchmark problems far HTR-10 and HTTR RCCS were assessed in order to assess the applicability of MARS code, a thermal-hydraulic safety analysis code developed for water reactors. The calculated results were compared with those or THERMIX, THANPACST2 code, and available experimental data. The calculated results showed generally good agreements with those obtained by the THERMIX code and THANPACST2 code. Deviations were analyzed to be originated from the simplification of complicated geometry and from the modeling capability of heat transfer characteristics in the HTGR components such as water cooler and air tooler. Especially, it was found that the radiation heat transfer in the reactor cavity played an important role in the after heat removal in the RCCS. Thus, it is concluded that MARS code can be successfully applied to the calculation of the RCCS cooling capability of the HTGR in this study.

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Assessment and Improvement of the Horizontal In-Tube Condensation Heat Transfer Model in the MARS code (MARS 코드의 수평관내부 응축열전달 모델 평가 및 개선)

  • Lee, Hyun Jin;Ahn, Tae Hwan;Yun, Byong Jo;Jeong, Jae Jun
    • Journal of Energy Engineering
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    • v.25 no.1
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    • pp.56-68
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    • 2016

  • Extensive researches have been carried out for enhancing the safety of nuclear power plants and, especially, the development of passive cooling systems, such as passive containment cooling system (PCCS) and passive residual heat removal system, is increasingly important, where condensation is a crucial heat transfer mechanism. Recently, Ahn & Yun et al. developed a horizontal in-tube condensation heat transfer model as one of the activities for the PCCS development. In this work, we implemented the Ahn & Yun 's condensation heat transfer model into the MARS code and assessed it using the PASCAL experimental data. Based on the results of the assessment, we identified the limitations of the Ahn & Yun 's model and suggested a modified Ahn & Yun 's model, and assessed the model using various experimental data.

  • https://doi.org/10.5855/ENERGY.2015.25.1.056 인용 PDF KSCI

Numerical Study of the Heat Removal Performance for a Passive Containment Cooling System using MARS-KS with a New Empirical Correlation of Steam Condensation (새로운 응축열전달계수 상관식이 적용된 MARS-KS를 활용한 원자로건물 피동냉각계통 열제거 성능의 수치적 연구)

  • Jang, Yeong-Jun;Lee, Yeon-Gun;Kim, Sin;Lim, Sang-Gyu
    • Journal of Energy Engineering
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    • v.27 no.4
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    • pp.27-35
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    • 2018

  • The passive containment cooling system (PCCS) has been designed to remove the released decay heat during the accident by means of the condensation heat transfer phenomenon to guarantee the safety of the nuclear power plant. The heat removal performance of the PCCS is mainly governed by the condensation heat transfer of the steam-air mixture. In this study, the heat removal performance of the PCCS was evaluated by using the MARS-KS code with a new empirical correlation for steam condensation in the presence of a noncondensable gas. A new empirical correlation implemented into the MARS-KS code was developed as a function of parameters that affect the condensation heat transfer coefficient, such as the pressure, the wall subcooling, the noncondensable gas mass fraction and the aspect ratio of the condenser tube. The empirical correlation was applied to the MARS-KS code to replace the default Colburn-Hougen model. The various thermal-hydraulic parameters during the operation of the PCCS follonwing a large-break loss-of-coolant-accident were analyzed. The transient pressure behavior inside the containment from the MARS-KS with the empirical correlation was compared with calculated with the Colburn-Hougen model.

  • https://doi.org/10.5855/ENERGY.2018.27.4.027 인용 PDF KSCI HTML