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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2014.12
- 수록면
- 112 - 122 (11page)
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초록· 키워드
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A main steam line break (MSLB) test at the ATLAS facility was simulated using the best-estimate thermal-hydraulic system code, MARS-KS. This has been performed as an activity at the third domestic standard problem for code benchmark (DSP-03) that has been organized by Korea Atomic Energy Research Institute (KAERI). The results of the MSLB experiment and the MARS input data prepared for the previous DSP-02 using the ATLAS facility were provided to participants. The preliminary MSLB simulation using the base input data, however, showed unphysical results in the primary-to-secondary heat transfer. To resolve the problems, some improvements were implemented in the MARS input modelling. These include the use of fine meshes for the bottom region of the steam generator secondary side and proper thermal-hydraulics calculation options. Other input model improvements in the heat loss and the flow restrictor models were also made and the results were investigated in detail. From the results of simulations, the limitations and further improvement areas of the MARS code were identified.
목차
Abstract
1. Introduction
2. Description of the ATLAS Facility
3. ATLAS MSLB Test
4. Input Model Modification for the MSLB Simulation
5. Results of Simulations and Discussions
6. Sensitivity Calculations
7. Concluding Remarks
References
참고문헌 (17)
참고문헌 신청
1. [학술지(정기간행물)] - J.J. Jeong / 1999 / Development of A Multi-dimensional Therma l-Hydraulic System Code, MARS 1.3.1 / Annals of Nuclear Energy 26 (18) : 1611 ~ 1642
2. [기타자료] - / 2009 / MARS code manual volume I: Code structur e, System Models, and Solution Methods / Korea Atomic Energy Research Institute
3. [학술지(정기간행물)] - J.-J. JEONG / 2005 / HOT CHANNEL ANALYSIS CAPABILITY OF THE BESTESTIMATEMULTI-DIMENSIONAL SYSTEM CODE, MARS3.0 / Nuclear Engineering and Technology 37 (5) : 469 ~ 478
4. [학술지(정기간행물)] - Jae Jun Jeong / 2010 / A coupled analysis of system thermal-hydrauli cs and three-dimensional reactor kinetics for a 12-finger control element assembly drop event in a PWR plant / Annals of Nuclear Energy 37 : 1580 ~ 1587
5. [학술지(정기간행물)] - B.G. Huh / 2010 / Best-estim ated evaluation for LBLOCA of APR1400 usi ng MARS code / Transactions of the America n Nuclear Society 103 : 501 ~ 502
2. [기타자료] - / 2009 / MARS code manual volume I: Code structur e, System Models, and Solution Methods / Korea Atomic Energy Research Institute
3. [학술지(정기간행물)] - J.-J. JEONG / 2005 / HOT CHANNEL ANALYSIS CAPABILITY OF THE BESTESTIMATEMULTI-DIMENSIONAL SYSTEM CODE, MARS3.0 / Nuclear Engineering and Technology 37 (5) : 469 ~ 478
4. [학술지(정기간행물)] - Jae Jun Jeong / 2010 / A coupled analysis of system thermal-hydrauli cs and three-dimensional reactor kinetics for a 12-finger control element assembly drop event in a PWR plant / Annals of Nuclear Energy 37 : 1580 ~ 1587
5. [학술지(정기간행물)] - B.G. Huh / 2010 / Best-estim ated evaluation for LBLOCA of APR1400 usi ng MARS code / Transactions of the America n Nuclear Society 103 : 501 ~ 502
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UCI(KEPA) : I410-ECN-0101-2017-572-000971033