Numerical simulation of the effect of rod bowing on critical heat flux
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Bing Ren
,
Shiyin Xu
Abstract
The paper demonstrates the CFD capability to predict the effect of rod bowing on CHF. The applicability and performance of the models are validated based on the Weatherhead experimental data for vertical pipe and NUPEC PWR subchannel and bundle test (PSBT) International Benchmark for rod bundle. The capability of the existing CFD method in predicting CHF is studied both qualitatively and quantitatively. Based on the validated method, the effect of the bowed rod on CHF is evaluated. The bow is assumed to occur at the midspan between two spacer grids in the region where DNB is predicted to occur. The results indicate that rod bowing has a deleterious effect on CHF, but this adverse bowing effect is dependent on the closure (i.e., the ratio of the change of the fuel rod gap to the nominal gap). There is no effect on CHF for closure between 0 and 50%, but adverse effect on CHF for closure larger than 50%, even more considerable effect as the closure increases to larger than 85%. The findings can be used to assist in designing the test fuel rod before the rod bowing CHF experiment.
Acknowledgement
The support provided by OECD/NEA and JNES is gratefully acknowledged. The data used in this study is from the OECD/PSBT benchmark of OECD/NEA and JNES.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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© 2021 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events
