Research on void drift between rod bundle subchannels
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
Void drift between subchannels in a rod bundle is a crucial phenomenon affecting the calculation accuracy of thermal-hydraulic parameters in SMRs. It holds significant importance in enhancing the precision of safety analysis for SMRs. Existing research on experiment and model of void drift between rod bundle subchannels is relatively rare, and the accuracy of model calculations requires improvement. In this study, experiments on gasliquid two-phase non-equilibrium flow were conducted to measure the redistribution of two-phase flow induced by void drift in a 1 × 2 rod bundle. The experiment results indicated that in bubby flow regime with void fraction less than 0.3, the void diffusion coefficient showed little variation with changes in void fraction. However, in slug flow and annular flow regimes with void fraction exceeding 0.3, the void diffusion coefficient significantly increased with an increase in void fraction. Furthermore, a new void drift model was developed and validated based on a subchannel code. The overall predicted uncertainty for the outlet void fraction in the rod bundle benchmark was less than 13%.
Abstract
Void drift between subchannels in a rod bundle is a crucial phenomenon affecting the calculation accuracy of thermal-hydraulic parameters in SMRs. It holds significant importance in enhancing the precision of safety analysis for SMRs. Existing research on experiment and model of void drift between rod bundle subchannels is relatively rare, and the accuracy of model calculations requires improvement. In this study, experiments on gasliquid two-phase non-equilibrium flow were conducted to measure the redistribution of two-phase flow induced by void drift in a 1 × 2 rod bundle. The experiment results indicated that in bubby flow regime with void fraction less than 0.3, the void diffusion coefficient showed little variation with changes in void fraction. However, in slug flow and annular flow regimes with void fraction exceeding 0.3, the void diffusion coefficient significantly increased with an increase in void fraction. Furthermore, a new void drift model was developed and validated based on a subchannel code. The overall predicted uncertainty for the outlet void fraction in the rod bundle benchmark was less than 13%.
참고문헌 (28)
- Guo Chengzhan, "Progress of operation and application on Shenzhen MNSR", Chinese Journal of Nuclear Science and Engineering, 20 (2000)
- Huai-kun Jiang, "Application of MNSR epithermal neutron activation analysis in determination of geological sample", Atomic Energy Sci. Technol, 49(8), pp.1488~ (2015)
- Li Yiguo, "Physics experimental study for reactor of in-hospital neutron irradiator", Atomic Energy Sci. Technol, 43 (2009)
- M. D. Carelli, "Handbook of Small Modular Nuclear Reactors" (2014)
- Chenglong Wang, "Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor", Int. J. Energy Res, 42(8), pp.2643~2654 (2018)
- Hang Xia, "Development of a thermo-mechanical coupling code based on an annular fuel sub-channel code", Nucl. Eng. Des, 355, pp.110284~ (2019)
- Yonghong Tian, "Sub-Channel analysis of Pb-Bi-cooled reactor with modified COBRA-EN", International Conference on Nuclear Engineering, pp.45912~ (2014), American Society of Mechanical Engineers
- J. T. Rogers, "Coolant Interchannel Mixing in Reactor Fuel Rod Bundles" (1969)
- R. T. Lahey Jr, "The Thermal-Hydraulics of a Boiling Water Nuclear Reactor" (1993)
- R. T. Lahey, "Mixing, Flow Regimes, and Void Fraction for Two-phase Flow in Rod Bundles" (1969)
- R. T. Lahey, "Out-of-pile subchannel measurements in a nine-rod bundle for water at 1000 psia", Proceedings of the International Symposium on Two-phase Systems, 6, pp.345~363 (1972)
- Jos´e M. Gonzalez-Santalo, "Two Phase Flow Mixing in Rod Bundle Subchannels", pp.1971
- Jr Lahey, T. Richard, "Subchannel measurements of the equilibrium quality and mass flux distribution in a rod bundle", International Heat Transfer Conference Digital Library (1986), Begel House Inc
- Y. Sato, "Two-phase flow characteristics in interconnected subchannels with different cross-sectional areas", Proc. 1987ASME• JSME Therm. Eng. Joint Cont, pp.389~395 (1987)
- A. Tapucu, "Experimental investigation of mass exchanges between two laterally interconnected two-phase flows", Nucl. Eng. Des, 105(3), pp.295~312 (1988)
- Sarman Gençay, "Lateral mixing mechanisms in vertical and horizontal interconnected subchannel two-phase flows", Nucl. Technol, 138(2), pp.140~161 (2002)
- Michio Sadatomi, "Flow redistribution due to void drift in two-phase flow in a multiple channel consisting of two subchannels", Nucl. Eng. Des, 148(2–3), pp.463~474 (1994)
- Michio Sadatomi, "Two-phase void drift phenomena in a 2× 3 rod bundle : flow redistribution data and their analysis", Nucl. Technol, 152(1), pp.23~37 (2005)
- M.P. Sharma, "Experimental investigation of void drift in simulated subchannels of a natural-circulation pressure tube–type BWR", Nuclear Science &Engineering the Journal of the American Nuclear Society, pp.1~12 (2017)
- A. Kawahara, "Void diffusion coefficient in two-phase void drift for several channels of two-and multi-subchannel systems", Multiphas. Sci. Technol, 18(1) (2006)
- Akimaro Kawahara, "Void diffusion coefficient in two-phase void drift for several channels of two-and multi-subchannel systems", Multiphas. Sci. Technol, 18, pp.1~ (2006)
- Ulrich Bieder, "LES analysis of the flow in a simplified PWR assembly with mixing grid", Prog. Nucl. Energy, 75, pp.15~24 (2014)
- I. I. I. L. D. Smith, "Benchmarking computational fluid dynamics for application to PWR fuel", International Conference on Nuclear Engineering, pp.35979~ (2002)
- Moys´es A. Navarro, "Evaluation of a numeric procedure for flow simulation of a 5× 5 PWR rod bundle with a mixing vane spacer", Prog. Nucl. Energy, 53(8), pp.1190~1196 (2011)
- Aleksandr Aleksandrovich Armand, "The resistance during the movement of a twophase system in horizontal pipes", Izv. Vses. Teplotekh. Inst, 1, pp.16~23 (1946)
- Salomon Levy, "Forced convection subcooled boiling—prediction of vapor volumetric fraction", Int. J. Heat Mass Tran, 10(7), pp.951~965 (1967)
- K. H. Sun, "The prediction of two-phase mixture level and hydrodynamically-controlled dryout under low flow conditions", Int. J. Multiphas. Flow, 7(5), pp.521~543 (1981)
- Two-phase Turbulent Mixing Model for Flow in Rod Bundles, "S. G. Beus", Bettis Atomic Power Lab, ~, pp.No. WAPD-T-2438; CONF-711112-6 (1972)
