کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
299559 511875 2006 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes
چکیده انگلیسی

A general critical heat flux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis at the conceptual design stage for a new pressurized water reactor (PWR). In this study, the Korea Advanced Institute of Science and Technology (KAIST) liquid sub-layer dryout CHF prediction model for Departure from Nucleate Boiling (DNB) region has been implemented in a sub-channel analysis code, and investigated for the method's possible use in a rod bundle environment with various non-uniform axial power shapes. The KAIST model showed comparable prediction capability to Lin's method for bottom-, center-, and top-peaked heat flux shapes. The KAIST model, without any correction factors or empirical constants, turned out to be suitable to fulfill the needs for a basis of a general CHF prediction method as compared to Lin's method and Westinghouse-3 (W-3) correlation.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 236, Issue 3, February 2006, Pages 223–231
نویسندگان
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