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contributor authorHernan Tinoco
contributor authorStefan Ahlinder
date accessioned2017-05-09T00:32:30Z
date available2017-05-09T00:32:30Z
date copyrightNovember, 2009
date issued2009
identifier issn1528-8919
identifier otherJETPEZ-27086#062903_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/140397
description abstractA thermal mixing analysis of the downcomer, main recirculation pumps (MRPs) and lower plenum of Forsmark’s Unit 3 has been carried out with three separate computational fluid dynamics models. Several difficulties with the boundary conditions have been encountered, particularly with the MRP model. The results obtained predict stable temperature differences of around 8 K at the core inlet. Such large temperature differences have never been observed at Forsmark nuclear power plant (NPP). Temperature measurements at four positions above the reactor pressure vessel (RPV) bottom give the mean value used as the core inlet temperature for core analyses. Even if the temperature transmitters used are rather slow and inaccurate, they should be able to detect such large temperature differences that may lead to fuel damage. The only damage reported at Forsmark NPP since the implementation of liner cladding in fuel design is that caused by mechanically induced debris fretting (threadlike particles). Also, the difficulties with the connection of the models throw some doubt on the accuracy of these predictions. A completely connected model of the same RPV volume covered by the separate models predicts temperature differences at core inlet that are almost one-fourth of those mentioned above, i.e., approximately 2.5 K. Most of the mixing occurs downstream of the MRP diffusers, at the lower plenum “inlet.” This prediction divergence seems to arise from an impossibility of a correct transfer of complete three-dimensional flow field properties by means of boundary conditions defined at a two-dimensional inlet section.
publisherThe American Society of Mechanical Engineers (ASME)
titleMixing Conditions in the Lower Plenum and Core Inlet of a Boiling Water Reactor
typeJournal Paper
journal volume131
journal issue6
journal titleJournal of Engineering for Gas Turbines and Power
identifier doi10.1115/1.3097130
journal fristpage62903
identifier eissn0742-4795
keywordsFlow (Dynamics)
keywordsTemperature
keywordsTurbulence
keywordsComputational fluid dynamics
keywordsPumps
keywordsBoundary-value problems
keywordsTemperature distribution
keywordsBoiling water reactors
keywordsKinetic energy
keywordsGeometry AND Reactor vessels
treeJournal of Engineering for Gas Turbines and Power:;2009:;volume( 131 ):;issue: 006
contenttypeFulltext


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