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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 829 - 841 (13page)
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초록· 키워드
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An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF),which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor(PWR). In the LSTF test, core uncovery started simultaneously with liquid level drop in crossover legdownflow-side before loop seal clearing, and water remaining occurred on the upper core plate in theupper plenum. Results of the uncertainty analysis with RELAP5/MOD3.3 code clarified the influences ofthe combination of multiple uncertain parameters on peak cladding temperature within the defineduncertain ranges. For studying the scaling problems to extrapolate thermal-hydraulic phenomenaobserved in scaled-down facilities, an experiment was performed for the OECD/NEA PKL-3 Project withthe Primarkreislaufe Versuchsanlage (PKL), as a counterpart to a previous LSTF test. The LSTF testsimulated a PWR 1% hot leg small-break loss-of-coolant accident with steam generator secondary-sidedepressurization as an accident management measure and nitrogen gas inflow. Some discrepanciesappeared between the LSTF and PKL test results for the primary pressure, the core collapsed liquid level,and the cladding surface temperature probably due to effects of differences between the LSTF and thePKL in configuration, geometry, and volumetric size.
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참고문헌 (28)
참고문헌 신청
R. Tregoning / 2008 / Estimating Loss-of-coolant Accident (LOCA) Frequencies through the Elicitation Process
The ROSA-V Group / 2003 / ROSA-v Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies
Y. Kukita / 1990 / The effects of break locaion on PWR small break LOCA: experimental study at the ROSA-IV LSTF / Nucl. Eng. Des 122:255~262
USNRC Nuclear Safety Analysis Division / 2001 / RELAP5/MOD3.3 Code Manual
S. Abe / 2014 / RELAP5 analyses on the influence of multi-dimensional flow in the core on core cooling during LSTF cold-leg intermediate break LOCA experiments in the OECD/NEA ROSA-2 Project / J. Nucl. Sci. Technol 51:1164~1176
The ROSA-V Group / 2003 / ROSA-v Large Scale Test Facility (LSTF) System Description for the Third and Fourth Simulated Fuel Assemblies
Y. Kukita / 1990 / The effects of break locaion on PWR small break LOCA: experimental study at the ROSA-IV LSTF / Nucl. Eng. Des 122:255~262
USNRC Nuclear Safety Analysis Division / 2001 / RELAP5/MOD3.3 Code Manual
S. Abe / 2014 / RELAP5 analyses on the influence of multi-dimensional flow in the core on core cooling during LSTF cold-leg intermediate break LOCA experiments in the OECD/NEA ROSA-2 Project / J. Nucl. Sci. Technol 51:1164~1176
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