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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 1,218 - 1,230 (13page)
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초록· 키워드
오류제보하기
A sub-channel solver, named Steady and Transient Analyzer for Reactor Thermal hydraulics (START), hasbeen developed using the homogenous model for two-phase conditions of light water reactors. The codeis developed as a fast and accurate TH-solver for coupled and multi-physics calculations. START has beenvalidated against the NUPEC PWR Sub-channel and Bundle Test (PSBT) database. Tests like singlechannelquality and void-fraction for steady state, outlet fluid temperature for steady state, rodbundlequality and void-fraction for both steady state and transient conditions have been analyzedand compared with experimental values. Results reveal a good accuracy of solution for both steady stateand transient scenarios. Axially different values for turbulent mixing coefficient are used based ondifferent grid-spacer types. This provides better results as compared to using a single value of turbulentmixing coefficient. Code-to-code evaluation of PSBT results by the START code compares well with otherindustrial codes. The START code has been parallelized with the OpenMP algorithm and its numericalperformance is evaluated with a large whole PWR core. Scaling study of START shows a good parallelperformance.
목차
등록된 정보가 없습니다.
참고문헌 (21)
참고문헌 신청
D. Basile / 1999 / COBRA-EN: an upgraded version of the COBRA-3C/MIT code for thermal hydraulic transient analysis of light water reactor fuel assemblies and cores
U. Imke / 2012 / Validation of the subchannel code SUBCHANFLOW using the NUPEC PWR tests (PSBT) / Sci. Technol. Nucl. Install 2012
D. -H. Hwang / 2012 / Accuracy and uncertainty analysis of PSBT benchmark exercises using a subchannel code MATRA / Sci. Technol. Nucl. Install :1~13
J.E. Kelly / THERMIT-2 : a Two-Fluid Model for Light Water Reactor Subchannel Transient Analysis
M. Avramova / 2013 / Comparative analysis of CTF and TRACE Thermal-Hydraulic codes using OECD/NRC PSBT benchmark void distribution database / Sci. Technol. Nucl. Install 2013
U. Imke / 2012 / Validation of the subchannel code SUBCHANFLOW using the NUPEC PWR tests (PSBT) / Sci. Technol. Nucl. Install 2012
D. -H. Hwang / 2012 / Accuracy and uncertainty analysis of PSBT benchmark exercises using a subchannel code MATRA / Sci. Technol. Nucl. Install :1~13
J.E. Kelly / THERMIT-2 : a Two-Fluid Model for Light Water Reactor Subchannel Transient Analysis
M. Avramova / 2013 / Comparative analysis of CTF and TRACE Thermal-Hydraulic codes using OECD/NRC PSBT benchmark void distribution database / Sci. Technol. Nucl. Install 2013
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