کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
296008 511702 2016 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Computational multi-fluid dynamics predictions of critical heat flux in boiling flow
ترجمه فارسی عنوان
پیش بینی های محاسباتی دینامیک های چند سیالات از شار حرارتی بحرانی در جریان جوش
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی


• A new mechanistic model dedicated to DNB has been implemented in the Neptune_CFD code.
• The model has been validated against 150 tests.
• Neptune_CFD code is a CFD tool dedicated to boiling flows.

Extensive efforts have been made in the last five decades to evaluate the boiling heat transfer coefficient and the critical heat flux in particular. Boiling crisis remains a major limiting phenomenon for the analysis of operation and safety of both nuclear reactors and conventional thermal power systems. As a consequence, models dedicated to boiling flows have being improved. For example, Reynolds Stress Transport Model, polydispersion and two-phase flow wall law have been recently implemented. In a previous work, we have evaluated computational fluid dynamics results against single-phase liquid water tests equipped with a mixing vane and against two-phase boiling cases. The objective of this paper is to propose a new mechanistic model in a computational multi-fluid dynamics tool leading to wall temperature excursion and onset of boiling crisis. Critical heat flux is calculated against 150 tests and the mean relative error between calculations and experimental values is equal to 8.3%. The model tested covers a large physics scope in terms of mass flux, pressure, quality and channel diameter. Water and R12 refrigerant fluid are considered. Furthermore, it was found that the sensitivity to the grid refinement was acceptable.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 299, 1 April 2016, Pages 28–36
نویسندگان
, , , , , ,