The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure

المؤلفون المشاركون

Shan, Jianqiang
Liu, Wei
Peng, Shinian
Jiang, Guangming
Liu, Yu

المصدر

Science and Technology of Nuclear Installations

العدد

المجلد 2019، العدد 2019 (31 ديسمبر/كانون الأول 2019)، ص ص. 1-14، 14ص.

الناشر

Hindawi Publishing Corporation

تاريخ النشر

2019-06-04

دولة النشر

مصر

عدد الصفحات

14

الملخص EN

The Critical Heat Flux (CHF) prediction under high pressure condition, even close to the vicinity of the critical pressure of water, is an important issue.

Although there are many empirical CHF correlations, most of them have covered the pressure under 15MPa.

In this study, based on the CHF experiment database of upflow boiling in vertical round tube from 15MPa to the vicinity of the critical pressure of water, the Katto, Bowring, Hall-Mudawar, Alekseev correlations, and Groeneveld LUT-2006 are comparatively studied.

With an error analysis of the predicted CHF to the experiment database, the prediction capability and the applicability of these correlations are evaluated and the parametric trends of CHF varying with pressure from 15MPa to critical pressure are proposed.

Simultaneously, according to the characteristics of Departure from Nucleate Boiling (DNB) type CHF under high pressure condition, the constitutive correlations of Weisman & Pei model are proposed.

The prediction results of three entrainment and deposition correlations of Kataoka, Celata, and Hewitt corresponding to the Dry-Out (DO) type CHF are analyzed.

Based on the two improved models above, a comprehensive CHF mechanistic model under high pressure condition combining the DNB and DO type CHF is established.

The verification based on the experiment database of upflow boiling in vertical round tube and the parametric trends analysis of CHF varying with thermal-hydraulic and geometric parameters are carried out.

Findings of this study have a positive effect on further development of CHF prediction method for universal CHF mechanism, especially under high pressure region.

نمط استشهاد جمعية علماء النفس الأمريكية (APA)

Liu, Wei& Shan, Jianqiang& Peng, Shinian& Jiang, Guangming& Liu, Yu. 2019. The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure. Science and Technology of Nuclear Installations،Vol. 2019, no. 2019, pp.1-14.
https://search.emarefa.net/detail/BIM-1210826

نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)

Liu, Wei…[et al.]. The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure. Science and Technology of Nuclear Installations No. 2019 (2019), pp.1-14.
https://search.emarefa.net/detail/BIM-1210826

نمط استشهاد الجمعية الطبية الأمريكية (AMA)

Liu, Wei& Shan, Jianqiang& Peng, Shinian& Jiang, Guangming& Liu, Yu. The Study of Critical Heat Flux in Upflow Boiling Vertical Round Tube under High Pressure. Science and Technology of Nuclear Installations. 2019. Vol. 2019, no. 2019, pp.1-14.
https://search.emarefa.net/detail/BIM-1210826

نوع البيانات

مقالات

لغة النص

الإنجليزية

الملاحظات

Includes bibliographical references

رقم السجل

BIM-1210826