基于COSINE软件包子通道软件的换热模型和氧化关系式适应性研究

程以炫; 孟召灿; 张昊; 章艺林; 赵萌; 杨燕华

doi:10.13832/j.jnpe.2024.04.0127

基于COSINE软件包子通道软件的换热模型和氧化关系式适应性研究

doi: 10.13832/j.jnpe.2024.04.0127

程以炫^1,,
孟召灿²,
张昊³,
章艺林²,
赵萌³,
杨燕华^{1, 3}

1.
上海交通大学国家电投智慧能源创新学院，上海，200240
2.
国家电投集团科学技术研究院有限公司，北京，102209
3.
上海交通大学核科学与工程学院，上海，200240

基金项目: 国防科工局核能开发项目

详细信息

作者简介:
程以炫（1995—），男，博士研究生，现主要从事核电软件开发与测试方面的研究，E-mail: cyx1995@sjtu.edu.cn

中图分类号: TL333
计量
- 文章访问数: 321
- HTML全文浏览量: 7
- PDF下载量: 10
- 被引次数: 0
出版历程
- 收稿日期: 2023-07-17
- 修回日期: 2024-01-10
- 刊出日期: 2024-08-12

Study on Adaptability of Heat Transfer Model and Oxidation Relationships Based on COSINE Sub-channel Code

1.
College of Smart Energy, Shanghai Jiao Tong University, Shanghai, 200240, China
2.
State Power Investment Corporation Research Institute, Beijing, 102209, China
3.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China

摘要

摘要: 针对压水堆核电子通道软件中换热模型和氧化关系式对提高堆芯安全性和国产化软件模拟预测准确性的急迫需求，采用数值模拟技术在COSINE软件包子通道软件中分析换热模型和氧化关系式，并运用实验数据研究了不同理论关系式对沸腾换热性能和氧化量的影响。结果表明，该软件具有模拟棒束内临界前后换热模型的能力，其模拟结果和实验值吻合良好。在过热度小于4 K前， MAX模型计算核态沸腾适用性较好；在过热度大于4 K后， PLUS模型适用性较好。Dougall-Rohsenow模型计算膜态沸腾适用性较好。Baker-Juster模型在温度低于1374 K前，略微高估氧化量；在温度高于1374 K后，低估氧化量。
- 子通道 /
- COSINE软件包 /
- 壁面换热 /
- 氧化量 /
- 适应性
Abstract: In view of the urgent need of heat transfer model and oxidation relationships in pressurized water reactor nuclear subchannel software to improve the core safety and the accuracy of simulation and prediction of domestic software, we used numerical simulation technology to analyze the heat transfer model and oxidation relationships in COSINE subchannel software, and used experimental data to study the influence of different theoretical relationships on boiling heat transfer performance and oxidation amount. The results indicate that the software has the ability to simulate the heat transfer before and after the criticality in the rod bundle, and the simulation results are in good agreement with the experimental values. Before the superheat degree is less than 4 K, the MAX model is suitable for calculating nucleate boiling. When the superheat degree is greater than 4 K, the PLUS model has good applicability. Dougall-Rohsenow model is suitable for calculating film boiling. Baker-Juster model slightly overestimated the oxidation amount before the temperature was lower than 1374 K; When the temperature is higher than 1374 K, the oxidation amount is underestimated.
- Subchannel /
- COSINE software package /
- Wall heat transfer /
- Oxidation amount /
- Adaptability

HTML全文

图 1 热流密度和壁面过热度的关系比较

Figure 1. Comparison of Relationship between Wall Heat Flux and Super Heat

下载: 全尺寸图片幻灯片

图 2 采用不同核态沸腾模型的数值模拟结果误差

Figure 2. Numerical Simulation Errors Using Different Nucleate Boiling Models

下载: 全尺寸图片幻灯片

图 3 THTF实验数据与不同膜态沸腾关系式比较

Figure 3. Comparison of THTF Experimental Data with Different Film Boiling Models

下载: 全尺寸图片幻灯片

图 4 采用不同膜态沸腾模型的数值模拟结果误差

Figure 4. Numerical Simulation Errors Using Different Film Boiling Models

下载: 全尺寸图片幻灯片

图 5 较低温度工况下氧化层厚度分布

Figure 5. Oxide Layer Thickness Distribution at Lower Temperature

下载: 全尺寸图片幻灯片

图 6 较高温度工况下氧化层厚度分布

Figure 6. Oxide Layer Thickness Distribution at Higher Temperature

下载: 全尺寸图片幻灯片

图 7 氧化量的数值模拟误差

Figure 7. Numerical Simulation Errors of Oxidation Amount

下载: 全尺寸图片幻灯片

表 1 理论模型工况实验范围

Table 1. Experimental Range of Theoretical Model Conditions

模型名称	适用范围
Jens-Lottes模型	p处于0.7~17.2 MPa，q小于12.5 MW/m²
Dittus-Boelter模型	流体被加热和冷却，普朗特数(Pr)指数分别为0.4和0.3
Thom模型	p处于5.2~13.8 MPa，q处于0.28~0.6 MW/m²
Groenveld模型	p处于3.45~21.37 MPa，含汽率(X)为0.1~ 0.9
Groenveld-Delorme模型	p处于0.69~21.37 MPa，X为0.12~0.31
Dougall-Rohsenow模型	p处于0.11~0.16 MPa，X为0.4
Baker-Juster模型	温度(T)处于1000~1300℃

下载: 导出CSV

参考文献(21)

[1]	于平安,朱瑞安,喻真烷,等. 核反应堆热工分析[M]. 上海: 上海交通大学出版社,2002: 48-60.
[2]	BROMLEY L A. Heat transfer in stable film boiling[J]. Chemical Engineering Progress, 1950, 46(5): 221-226.
[3]	刘彦章,邱军,刘欣,等. N18锆合金在600~1200℃蒸汽中的氧化行为研究[J]. 核动力工程,2010, 31(2): 85-88.
[4]	DITTUS F W, BOELTER L M K. Heat transfer in automobile radiators of the tubular type[J]. University of California Publications in Engineering, 1930, 2: 443-461.
[5]	ONG’IRO A, UGURSAL V I, AL TAWEEL A M, et al. Modeling of heat recovery steam generator performance[J]. Applied Thermal Engineering, 1997, 17(5): 427-446. doi: 10.1016/S1359-4311(96)00052-X
[6]	JENS W H, LOTTES P A. Analysis of heat transfer, burnout, pressure drop and density date for high-pressure water: ANL-4672[R]. Argonne: Argonne National Laboratory, 1951.
[7]	GROENEVELD D C, MOECK E O. An investigation of heat transfer in the liquid deficient regime: AECL-3281[R]. Chalk River: Chalk River Nuclear Labs, 1969.
[8]	GROENEVELD D C, DELORME G G J. Prediction of thermal non-equilibrium in the post-dryout regime[J]. Nuclear Engineering and Design, 1976, 36(1): 17-26. doi: 10.1016/0029-5493(76)90138-2
[9]	DOUGALL R L, ROHSENOW W M. Film-boiling on the inside of vertical tubes with upward flow of the fluid at low qualities[D]. Cambridge: Doctoral dissertation, Massachusetts Institute of Technology, 1973.
[10]	MARTÍN-CALLIZO C, PALM B, OWHAIB W. Subcooled flow boiling of R-134a in vertical channels of small diameter[J]. International Journal of Multiphase Flow, 2007, 33(8): 822-832. doi: 10.1016/j.ijmultiphaseflow.2007.02.002
[11]	TONG L S, YOUNG J D. Phenomenological transition and film boiling heat transfer correlation[C]// International Heat Transfer Conference. Tokyo, 1974.
[12]	EBRAHIM S A. An experimental investigation of the effects of surface conditions on pool-boiling heat transfer for various materials[D]. State College: The Pennsylvania State University, 2018.
[13]	李智. 天然气发动机气缸盖热负荷及冷却水腔内沸腾传热研究[D]. 武汉: 华中科技大学,2012.
[14]	傅松. 缸盖冷却水套内沸腾传热特性的研究[D]. 济南: 山东大学,2010.
[15]	CATHCART J V, PAWEL R E, MCKEE R A, et al. Zirconium metal-water oxidation kinetics: IV reaction rate studies: ORNL/NUREG-17[R]. Oak Ridge: Oak Ridge National Laboratory, 1977.
[16]	HU X G, DONG C, WANG Q, et al. High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings[J]. Journal of Nuclear Materials, 2019, 519: 145-156. doi: 10.1016/j.jnucmat.2019.01.039
[17]	YEOM H, MAIER B, JOHNSON G, et al. High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments[J]. Journal of Nuclear Materials, 2019, 526: 151737. doi: 10.1016/j.jnucmat.2019.151737
[18]	葛炜,杨燕华,刘飒,等. 大型先进压水堆核电站关键设计软件自主化与COSINE软件包研发[J]. 中国能源,2016, 38(7): 39-44.
[19]	傅孝良,刘丽芳,于楠,等. COSINE系统分析程序模型评估需求分析[J]. 核动力工程,2015, 36(1): 144-147.
[20]	ROHSENOW W M, CLARK J A. Heat transfer and pressure drop data for high heat flux densities to water at high subcritical pressures: NP-3385[R]. Cambridge, Mass.: MIT Division of Industrial Cooperation, 1951.
[21]	YODER G L, MORRIS D G, MULLINS C B, et al. Dispersed-flow film boiling in rod-bundle geometry: steady-state heat-transfer data and correlation comparisons. [PWR; BWR]: NUREG/CR-2435[R]. Oak Ridge: Oak Ridge National Laboratory, 1982. DOI: 10.2172/5425380.