Subchannel analysis
WebASSERT-PV has been developed at AECL to meet the specific requirements for subchannel thermalhydraulic analysis of two-phase flows in horizontally oriented CANDU fuel bundles. It provides detailed flow and phase distributions in subchannels of a fuel bundle to evaluate CHF, post-dryout heat transfer, and fuel-sheath temperature. WebDetermination of turbulent mixing rate of two phase flow between neighboring subchannels is an important aspect of sub channel analysis in reactor rod bundles. Various models …
Subchannel analysis
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Web2 Feb 2011 · Subchannel analyses methods are based upon radial solution meshes within the fuel assemblies. Subchannel methods divide fuel assemblies into a number of … WebCOOLOD-N code ( Kaminaga Masanori, 1994) was developed for the analysis of the steady-state parameters of plate-type fuel reactors, especially for the upgraded JRR-3. RETRAC-PC ( Bousbia-Salah and Hamidouche, 2005 ), was developed to …
WebThe subchannel code SUBCAL and CFD code ANSYS Fluent with the Reynolds stress turbulence model, which is capable of solving the anisotropic flow present in rod … WebA subchannel analysis program, MENUETT, is developed for evaluation of thermal-hydraulic characteristics in boiling water reactor fuel bundles. This program is based on five …
Web8 Feb 2024 · In JAEA, an in-house subchannel analysis code named thermal-hydraulic analysis of asymmetrical flow in reactor elements (ASFRE) has been developed as a FA design tool. For the typical FAs, the numerical results of ASFRE had been validated by comparisons with experimental data, in the previous study. Web1 Dec 2024 · The validations and experimental benchmarking are discussed for subchannel analysis. Also found in this paper are recent developments in direct modeling of mixing …
Web26 Jun 2016 · Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF Published by De Gruyter June 11, 2016 Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF Bao-Wen Yang, Yassin A. Hassan, Hisashi Ninokata, Jianqiang Shan, Yuxiang Zhang and Bin Zhang
Webanalysis can be satisfied by the scheduling of maintenance activities. The analysis of non-reactor faults is sufficient for GDA and there are no faults arising within the waste route … my outlook says working offlineWebCTF analysis with the parameter set identified by the data assimilation was conducted, and it was confirmed that the average value of the bundle-averaged void fraction improved … my outlook says work offlineWeb26 Jun 2016 · Abstract A subchannel analysis of the steam cooling data obtained in the Rod Bundle Heat Transfer (RBHT) test facility has been performed in this study to capture the … my outlook says it is disconnectedWeb26 Jun 2016 · Article Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF was published on June 26, 2016 in the journal … my outlook scheduling assistant disappearedWebIn the PWR reactor core, the power profile is nonuniform and the inter-subchannel mixing is of great importance for flatting the temperature distribution of the coolant and for reactor … old-fashioned corn starch custard puddingWeb12 Apr 2024 · The comparison and verification with the simulation calculation results of the MTR reactor under steady-state conditions with the FLUENT and MATRA codes show that the developed subchannel code can simulate the thermal-hydraulic phenomena of … my outlook screen is too smallWeb26 Jun 2016 · A subchannel analysis of the steam cooling data obtained in the Rod Bundle Heat Transfer (RBHT) test facility has been performed in this study to capture the effect … my outlook screen shrunk