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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 466 - 475 (10page)
이용수
초록· 키워드
오류제보하기
Coolant mixing under natural circulation flow regime constitutes a key parameter that mayplay a role in the course of an accidental transient in a nuclear pressurized water reactor.
This issue has motivated some experimental investigations carried out within the OECD/NEA PKL projects. The aim was to assess the coolant mixing phenomenon in the reactorpressure vessel downcomer and the core lower plenum under several asymmetric steadyand unsteady flow conditions, and to provide experimental data for code validations. Formerstudies addressed the mixing phenomenon using, on the one hand, one-dimensionalcomputational approaches with cross flows that are not fully validated under transientconditions and, on the other hand, expensive computational fluid dynamic tools thatare not always justified for large-scale macroscopic phenomena. In the current framework,an unsteady coolant mixing experiment carried out in the Rossendorf coolant mixingtest facility is simulated using the three-dimensional porous media capabilities ofthe thermalehydraulic system CATHARE code. The current study allows highlighting thecurrent capabilities of these codes and their suitability for reproducing the main phenomenaoccurring during asymmetric transient natural circulation mixing conditions.
목차
등록된 정보가 없습니다.
참고문헌 (17)
참고문헌 신청
A. Bousbia Salah / 2007 / Use of coupled code technique for best estimate safety analysis of nuclear power plants / Prog. Nucl. Energy 49 : 1 ~ 13
A. Bousbia Salah / 2013 / Assessment of the CATHARE 3D capabilities in predicting the temperature mixing under asymmetric buoyant driven flow conditions / Nucl. Eng. Des 265
A. Bousbia Salah / 2015 / Experimental and analytical assessment of natural circulation interruption phenomenon in the LSTF and PKL test facilities / ANS Nucl. Technol 192 :
CSNI / 2014 / Assessment of CFD codes for nuclear reactor safety problems
G. Lavialle / 2010 / The CATHARE2_V2.5_2mod8.1 code: main features / EN/CAD/DER/SSTH/LDLD/EM/NT/ 2010-033/A
A. Bousbia Salah / 2013 / Assessment of the CATHARE 3D capabilities in predicting the temperature mixing under asymmetric buoyant driven flow conditions / Nucl. Eng. Des 265
A. Bousbia Salah / 2015 / Experimental and analytical assessment of natural circulation interruption phenomenon in the LSTF and PKL test facilities / ANS Nucl. Technol 192 :
CSNI / 2014 / Assessment of CFD codes for nuclear reactor safety problems
G. Lavialle / 2010 / The CATHARE2_V2.5_2mod8.1 code: main features / EN/CAD/DER/SSTH/LDLD/EM/NT/ 2010-033/A
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