Study on Orthogonal Experiments of Jet Breakup and its Modeling Based on MPS Method

Peng Cheng; Meng Xianpin; Deng Jian

doi:10.13832/j.jnpe.2024.04.0181

Volume 45 Issue 4

Aug. 2024

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2024 > 45(4): 181-189

Peng Cheng, Meng Xianpin, Deng Jian. Study on Orthogonal Experiments of Jet Breakup and its Modeling Based on MPS Method[J]. Nuclear Power Engineering, 2024, 45(4): 181-189. doi: 10.13832/j.jnpe.2024.04.0181

Citation:

Peng Cheng, Meng Xianpin, Deng Jian. Study on Orthogonal Experiments of Jet Breakup and its Modeling Based on MPS Method[J]. Nuclear Power Engineering, 2024, 45(4): 181-189. doi: 10.13832/j.jnpe.2024.04.0181

Citation:

PDF( 5499 KB)

Study on Orthogonal Experiments of Jet Breakup and its Modeling Based on MPS Method

doi: 10.13832/j.jnpe.2024.04.0181

1.
College of Energy and Mechanical Engineering, Shanghai University of Electric Power, Shanghai, 200090, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-08-17
Rev Recd Date: 2024-01-15
Publish Date: 2024-08-12

Abstract

Abstract

In order to study the primary influencing factors of jet breakup length during the core melt jet breakup process and their ranking, 25 sets of experiments with 3 factors and 5 levels were designed based on the orthogonal experimental method, and the jet breakup lengths were obtained for each condition by using the Moving Particle Semi-implicit method (MPS). The simulation results were analyzed by polarity and variance analysis, and it was concluded that the primary influencing factors of jet breakup length were jet to coolant density ratio, jet velocity and jet diameter, and all of them have a second level of significance (**). Their ranking in the same level was in the following order: jet velocity > jet to coolant density ratio > jet diameter. Moreover, a new empirical relationship for predicting jet breakup length was fitted using simulated data, and the error margin of the model was kept within ±30% when the ratio of jet to coolant density was 1.1~13.6.
- Jet breakup length,
- Influencing factors,
- Orthogonal experiments,
- Empirical correlation

FullText(HTML)

References(28)

References

[1]	THEOFANOUS T G, SAITO M. An assessment of Class-9 (core-melt) accidents for PWR dry-containment systems[J]. Nuclear Engineering and Design, 1981, 66(3): 301-332. doi: 10.1016/0029-5493(81)90162-X
[2]	BRAYER C, LE MONNIER A, CHIKHI N. Impact of corium thermophysical properties on fuel-coolant interaction[J]. Annals of Nuclear Energy, 2020, 147: 107613. doi: 10.1016/j.anucene.2020.107613
[3]	彭程,邓坚. 蒸汽夹带作用下高温颗粒表面拖曳力模型研究[J]. 核动力工程,2022, 43(6): 61-65.
[4]	SUN R Y, WU L P, DING W, et al. From melt jet break-up to debris bed formation: a review of melt evolution model during fuel-coolant interaction[J]. Annals of Nuclear Energy, 2022, 165: 108642. doi: 10.1016/j.anucene.2021.108642
[5]	CORRADINI M L, KIM B J, OH M D. Vapor explosions in light water reactors: a review of theory and modeling[J]. Progress in Nuclear Energy, 1988, 22(1): 1-117. doi: 10.1016/0149-1970(88)90004-2
[6]	TAYLOR G I. Scientific papers. Vol. Ⅲ: aerodynamics and the mechanics of projectiles and explosions [M]. New York: Cambridge University Press, 1963: 287-303.
[7]	EPSTEIN M, FAUSKE H K. Applications of the turbulent entrainment assumption to immiscible gas-liquid and liquid-liquid systems[J]. Chemical Engineering Research and Design, 2001, 79(4): 453-462. doi: 10.1205/026387601750282382
[8]	MATSUO E, ABE Y, CHITOSE K, et al. Study on jet breakup behavior at core disruptive accident for fast breeder reactor[J]. Nuclear Engineering and Design, 2008, 238(8): 1996-2004. doi: 10.1016/j.nucengdes.2007.11.011
[9]	SAITO M, SATO K, IMAHORI S. Experimental study on penetration behaviors of water jet into Freon-11 and liquid nitrogen [C]. Houston: Proceeding of 1988 National Heat Transfer Conference, 1988.
[10]	KOSHIZUKA S, NOBE A, OKA Y. Numerical analysis of breaking waves using the moving particle semi-implicit method[J]. International Journal for Numerical Methods in Fluids, 1998, 26(7): 751-769. doi: 10.1002/(SICI)1097-0363(19980415)26:7<751::AID-FLD671>3.0.CO;2-C
[11]	PARK S, PARK H S, JANG B I, et al. 3-D simulation of plunging jet penetration into a denser liquid pool by the RD-MPS method[J]. Nuclear Engineering and Design, 2016, 299: 154-162. doi: 10.1016/j.nucengdes.2015.08.003
[12]	CAI Q H, CHEN R H, GUO K L, et al. An enhanced moving particle semi-implicit method for simulation of incompressible fluid flow and fluid-structure interaction[J]. Computers & Mathematics with Applications, 2023, 145: 41-57.
[13]	BRACKBILL J U, KOTHE D B, ZEMACH C. A continuum method for modeling surface tension[J]. Journal of Computational Physics, 1992, 100(2): 335-354. doi: 10.1016/0021-9991(92)90240-Y
[14]	DING W, XIAO X K, CAI Q H, et al. Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM[J]. Annals of Nuclear Energy, 2022, 175: 109244. doi: 10.1016/j.anucene.2022.109244
[15]	TIAN W X, QIU S Z, SUI G H, et al. Numerical solution on spherical vacuum bubble collapse using MPS method[J]. Journal of Engineering for Gas Turbines and Power, 2010, 132(10): 102920. doi: 10.1115/1.4001058
[16]	CHEN R H, CAI Q H, ZHANG P H, et al. Three-dimensional numerical simulation of the HECLA-4 transient MCCI experiment by improved MPS method[J]. Nuclear Engineering and Design, 2019, 347: 95-107. doi: 10.1016/j.nucengdes.2019.03.024
[17]	CAI Q H, ZHU D H, CHEN R H, et al. Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method[J]. Annals of Nuclear Energy, 2020, 144: 107525. doi: 10.1016/j.anucene.2020.107525
[18]	陈荣华, 田文喜, 左娟莉, 等. 基于MPS方法的液态铅铋合金内气泡上升流数值模拟[J]. 核动力工程,2011,32(5): 96-99. 陈荣华, 田文喜, 左娟莉, 等. 基于MPS方法的液态铅铋合金内气泡上升流数值模拟[J]. 核动力工程, 2011,32(5): 96-99.
[19]	MEIGNEN R, RAVERDY B, PICCHI S, et al. The challenge of modeling fuel-coolant interaction: Part II -Steam explosion[J]. Nuclear Engineering and Design, 2014, 280: 528-541. doi: 10.1016/j.nucengdes.2014.08.028
[20]	CHENG H, ZHAO J Y, WANG J. Experimental investigation on the characteristics of melt jet breakup in water: the importance of surface tension and Rayleigh-Plateau instability[J]. International Journal of Heat and Mass Transfer, 2019, 132: 388-393. doi: 10.1016/j.ijheatmasstransfer.2018.12.026
[21]	NISHIMURA S, SUGIYAMA K I, KINOSHITA I, et al. Fragmentation mechanisms of a single molten copper jet penetrating a sodium pool-transition from thermal to hydrodynamic fragmentation in instantaneous contact interface temperatures below its freezing point[J]. Journal of Nuclear Science and Technology, 2010, 47(3): 219-228. doi: 10.1080/18811248.2010.9711948
[22]	CHU C C, SIENICKI J J, SPENCER B W, et al. Ex-vessel melt-coolant interactions in deep water pool: studies and accident management for Swedish BWRs[J]. Nuclear Engineering and Design, 1995, 155(1-2): 159-213. doi: 10.1016/0029-5493(94)00874-X
[23]	DINH T N, BUI V A, NOURGALIEV R R, et al. Experimental and analytical studies of melt jet-coolant interactions: a synthesis[J]. Nuclear Engineering and Design, 1999, 189(1-3): 299-327. doi: 10.1016/S0029-5493(98)00275-1
[24]	THAKRE S, MANICKAM L, MA W M. A numerical simulation of jet breakup in melt coolant interactions[J]. Annals of Nuclear Energy, 2015, 80: 467-475. doi: 10.1016/j.anucene.2015.02.038
[25]	李云雁,胡传荣. 试验设计与数据处理[M]. 第三版. 北京: 化学工业出版社,2017: 68-75.
[26]	CHEN J T, ZHOU Y, ZHAO J Y, et al. Experimental and theoretical study of jet hydrodynamic breakup behavior with air entrainment[J]. Annals of Nuclear Energy, 2021, 151: 107900. doi: 10.1016/j.anucene.2020.107900
[27]	JUNG W H, PARK H S, MORIYAMA K, et al. Analysis of experimental uncertainties in jet breakup length and jet diameter during molten fuel-coolant interaction[J]. Nuclear Engineering and Design, 2019, 344: 183-194. doi: 10.1016/j.nucengdes.2019.01.018
[28]	MORIYAMA K, MARUYAMA Y, USAMI T, et al. Coarse break-up of a stream of oxide and steel melt in a water pool: JAERI-Research-2005-017[R]. Kashiwa: Japan Atomic Energy Research Institute, 2005.