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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2012.1
- 수록면
- 249 - 260 (12page)
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Main focus of the combined nuclear research activities at Aachen University (RWTH) and the Research Center Jich (JICH) is the experimental and analytical investigation of containment phenomena and processes. We are deeply convinced that reliable simulations for operation, design basis and beyond-design basis accidents of nuclear power plants need the application of so-called lumped-parameter (LP) based codes as well as computational fluid dynamics (CFD) codes in an indispensable manner. The LP code being used at our institutions is the GRS code COCOSYS and the CFD tool is ANSYS CFX mostly used in German nuclear research. Both codes are applied for safety analyses especially of beyond design accidents.
Focal point of the work is containment thermal-hydraulics, but source term relevant investigations for aerosol and iodine behavior are performed as well. To increase the capability of COCOSYS and CFX detailed models for specific features, e.g.
recombiner behavior including chimney effect, building condenser, and wall condensation are developed and validated against facilities at different scales. The close connection between analytical and experimental activities is notable and identifying feature of the RWTH/JICH activities.
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참고문헌 (28)
참고문헌 신청
ANSYS Inc / 2006 / ANSYS CFX Solver Theory Guide - CFX Release 11.0 / Ansys Inc
B. Huttermann / 1999 / Analysis of large pools (containment cooler) (COCOSYS/CFX analysis of the PANDA building condenser experiment BC4 with large external pool)
B. Huttermann / 2001 / Analysis of PANDA BC3 and BC4 test with focus to the energy balance by the COCOSYS code
B. Smith / 2008 / Assessment of CFD for nuclear reactor safety / Proc. OECD/NEA & IAEA Workshop: Experiments and CFD code applications to nuclear reactor safety XCFD4NRS, NEA/C
D. Bestion / 2004 / Recommendation on the use of CFD codes for nuclear reactor safety analysis / EVOL-ECORAD14, 5th EURATOM Framework Program
B. Huttermann / 1999 / Analysis of large pools (containment cooler) (COCOSYS/CFX analysis of the PANDA building condenser experiment BC4 with large external pool)
B. Huttermann / 2001 / Analysis of PANDA BC3 and BC4 test with focus to the energy balance by the COCOSYS code
B. Smith / 2008 / Assessment of CFD for nuclear reactor safety / Proc. OECD/NEA & IAEA Workshop: Experiments and CFD code applications to nuclear reactor safety XCFD4NRS, NEA/C
D. Bestion / 2004 / Recommendation on the use of CFD codes for nuclear reactor safety analysis / EVOL-ECORAD14, 5th EURATOM Framework Program
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