Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

المؤلفون المشاركون

Petrov, Victor
Manera, Annalisa
Kim, Taewan
Lo, Simon

المصدر

Science and Technology of Nuclear Installations

العدد

المجلد 2012، العدد 2012 (31 ديسمبر/كانون الأول 2012)، ص ص. 1-20، 20ص.

الناشر

Hindawi Publishing Corporation

تاريخ النشر

2012-10-11

دولة النشر

مصر

عدد الصفحات

20

التخصصات الرئيسية

العلوم الهندسية و تكنولوجيا المعلومات

الملخص EN

In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC, the subchannel code FLICA4 developed by CEA, and the computational fluid dynamic code STAR-CD developed by CD-adapco.

The PSBT benchmark consists of a series of void distribution exercises and departure from nucleate boiling exercises.

The results reveal that the prediction by the subchannel code FLICA4 agrees with the experimental data reasonably well in both steady-state and transient conditions.

The analyses of single-subchannel experiments by means of the computational fluid dynamic code STAR-CD with the CD-adapco boiling model indicate that the prediction of the void fraction has no significant discrepancy from the experiments.

The analyses with TRACE point out the necessity to perform additional assessment of the subcooled boiling model and bulk condensation model of TRACE.

نمط استشهاد جمعية علماء النفس الأمريكية (APA)

Kim, Taewan& Petrov, Victor& Manera, Annalisa& Lo, Simon. 2012. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-20.
https://search.emarefa.net/detail/BIM-495418

نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)

Kim, Taewan…[et al.]. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-20.
https://search.emarefa.net/detail/BIM-495418

نمط استشهاد الجمعية الطبية الأمريكية (AMA)

Kim, Taewan& Petrov, Victor& Manera, Annalisa& Lo, Simon. Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes. Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-20.
https://search.emarefa.net/detail/BIM-495418

نوع البيانات

مقالات

لغة النص

الإنجليزية

الملاحظات

Includes bibliographical references

رقم السجل

BIM-495418