Critical Heat Flux in Square- and Nonsquare-Array Rod Bundles for Advanced Light Water Reactors

2007 ◽  
Vol 158 (2) ◽  
pp. 219-228 ◽  
Author(s):  
Dae-Hyun Hwang ◽  
Kyong-Won Seo ◽  
Chung-Chan Lee
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Light Water Reactors ◽  
Rod Bundles ◽  
Light Water ◽  
Water Reactors

scholarly journals Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments

2014 ◽  
Vol 2014 ◽  
pp. 1-9 ◽  
Author(s):  
Baowen Yang ◽  
Jianqiang Shan ◽  
Junli Gou ◽  
Hui Zhang ◽  
Aiguo Liu ◽  
...  
Keyword(s):  
Power Distribution ◽  
Fundamental Difference ◽  
Heat Fluxes ◽  
Correction Factors ◽  
Light Water Reactors ◽  
Rod Bundles ◽  
Light Water ◽  
Driving Mechanisms ◽  
Rod Bundle ◽  
Water Reactors

Rod bundle experiments with axially uniform and nonuniform heat fluxes are examined to explore the potential limitations of using uniform rod bundle CHF data for CHF correlation development of light water reactors with nonuniform axial power distribution (APD). The case of upstream burnout is presented as an example of unique phenomena associated with nonuniform rod bundle CHF experiments. It is a result from combined effect of axial nonuniform power shape and different interchannel mixing mechanisms. In addition, several key parameters are investigated with respect to their potential impacts on the thermal-hydraulic behaviors between rod bundles with uniform and nonuniform APDs. This type of misrepresentation cannot be amended or compensated through the use of correction factors due to the lack of critical information in the uniform rod bundle CHF testing as well as the fundamental difference in the underlining driving mechanisms. Other potential issues involved with the use of uniform rod bundle CHF data for nonuniform APD system applications also present strong evidence concerning the limitations and inadequacy of using uniform rod bundle CHF data for the correlation, prediction, and design limit calculation for safety analysis.

Experimental Studies on Critical Heat Flux in Tight Lattice Rod Bundles

2014 ◽  
Author(s):  
Xuemei Lang ◽  
Houjun Gong ◽  
Lei Zhou ◽  
Feng Xie ◽  
Ye Liu
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Experimental Studies ◽  
Helix Angle ◽  
Pressurized Water Reactors ◽  
Experimental Investigations ◽  
Rod Bundles ◽  
Pressurized Water ◽  
Water Reactors ◽  
Tight Lattice

The tight fuel lattice of pressurized water reactors (PWR) is helped to reduce the volume ratio of water-uranium, to increase the conversion ratio, to decrease the volume of core. It is especially useful for very high burnup and high volume power flux. The design of tight-lattice pressurized water reactors requires the knowledge of critical heat flux (CHF) in tight rod bundles. The tight hexagonal 19-rod bundles is used in this test. There are 4 wires wrapped in outside wall of each rod to support and locate. Experimental investigations on CHF behavior in the two kind bundles of helix angle 3° and 5° were performed. The CHF data points have been obtained in a range of parameters: pressure 8.0–16.6 MPa, mass flux 164.6–3283.0 kg/m2s and bundle exit steam quality −0.315 to 0.747. It is found that the CHF value of helix angle 5° bundle was more higher than that of helix angle 3° bundle in the same T/H condition. The effect of different parameters on CHF in the tight rod bundle is similar to that in the open literature. The CHF correlations of helix angle 5° bundle was obtained based on the test data.

A new approach to spent nuclear fuel recycling for light water reactors in the frame of remix concept

2020 ◽  
Vol 2020 (1) ◽  
pp. 67-77
Author(s):  
Nikita Vladimirivich Kovalyov ◽  
Boris Yakovlevich Zilberman ◽  
Nikolay Dmitrievich Goletskiy ◽  
Andrey Borisovich Sinyukhin
Keyword(s):  
Nuclear Fuel ◽  
Spent Nuclear Fuel ◽  
Light Water Reactors ◽  
New Approach ◽  
Light Water ◽  
Water Reactors

Use of Thorium in Light Water Reactors

2005 ◽  
Vol 151 (2) ◽  
pp. 168-176 ◽  
Author(s):  
Michael Todosow ◽  
A. Galperin ◽  
S. Herring ◽  
M. Kazimi ◽  
T. Downar ◽  
...  
Keyword(s):  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors
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