聚变堆液态包层增殖区铅锂与氦气多流场耦合换热特性研究

doi:10.16568/j.0254-6086.201904004

核聚变与等离子体物理 ›› 2019, Vol. 39 ›› Issue (4): 309-316.DOI: 10.16568/j.0254-6086.201904004

聚变堆液态包层增殖区铅锂与氦气多流场耦合换热特性研究

汪卫华1, 2，程德胜2，邓海飞2，王晓宇3，储德林1，刘胜1

(1. 安徽大学物质科学与信息技术研究院，合肥 230061； 2. 陆军炮兵防空兵学院，合肥 230031； 3. 核工业西南物理研究院，成都 610041)

收稿日期:2018-10-30 修回日期:2019-07-02 出版日期:2019-12-15 发布日期:2019-12-16
作者简介:汪卫华(1965-)，男，安徽望江人，教授，主要从事聚变堆堆内部件关键技术研发与实验研究。
基金资助:
国家自然科学基金(51576208)；国家重点研发计划(2017YFE0300603)；国家磁约束核聚变能发展研究专项(2015GB121007，2015GB102004)；安徽省自然科学基金(1708085MA09，1708085QB32)

Coupled heat transfer characteristics study of multi-flow field between lead lithium and helium gas for liquid blanket breeder zone of fusion reactor

WANG Wei-hua1, 2, CHENG De-sheng2, DENG Hai-fei2, WANG Xiao-yu3, CHU De-lin1, LIU Sheng1

(1. Institute of Physical Science and Information Technology, Anhui University, Hefei 230061; 2. Institute of Applied Physics, PLA Army Academy of Artillery & Air Defense, Hefei 230031; 3. Southwestern Institute of Physics, Chengdu 610041)

Received:2018-10-30 Revised:2019-07-02 Online:2019-12-15 Published:2019-12-16

摘要/Abstract

摘要：

采用三维计算流体动力学(CFD)方法对聚变堆液态包层增殖区高温液态铅锂与结构内高压氦气耦合换热进行数值模拟。建立了充放式高压氦气回路和换热实验段，开展了包层典型工况下液态铅锂与氦气多流场耦合换热对比实验验证。研究了氦气压力和增殖区铅锂入口温度、核热功率密度变化时的流动与传热特性及其影响规律，获得了氦气与RAFM钢壁面、液态铅锂与RAFM钢壁面之间的换热系数和换热关联式，为液态包层的设计研发提供了参考依据。

关键词: 液态铅锂包层, 多流场, 氦气, 耦合换热

Abstract:

The coupled heat transfer of multi-flow field in liquid blanket breeder zone of fusion reactor has been simulated by three-dimension computational fluid dynamics (CFD) method. The filling-evacuating high-pressure helium-cooled loop and the heat exchange test module have been built, and the contrast experiments of coupled heat transfer of multi-flow field have been implemented for validating numerical calculation results. The flow and heat transfer characteristics, and its effect on the condition of varied helium gas operational pressure and liquid lead lithium inlet temperature, nuclear heat power density in breeder zone were studied. The heat transfer coefficient and correlation formula of helium and RAFM steel surface, liquid lead lithium and RAFM steel surface were presented. The results will be beneficial for the design, research and development of liquid blanket.

Key words: Liquid lead lithium blanket, Multi-flow field, Helium gas, Coupled heat transfer

中图分类号:

TL62+1

汪卫华1, 2，程德胜2，邓海飞2，王晓宇3，储德林1，刘胜1. 聚变堆液态包层增殖区铅锂与氦气多流场耦合换热特性研究[J]. 核聚变与等离子体物理, 2019, 39(4): 309-316.

WANG Wei-hua1, 2, CHENG De-sheng2, DENG Hai-fei2,WANG Xiao-yu3, CHU De-lin1, LIU Sheng1. Coupled heat transfer characteristics study of multi-flow field between lead lithium and helium gas for liquid blanket breeder zone of fusion reactor[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 309-316.

参考文献

[1] Abdou M, Morley N B, Smolentsev S, et al. Blanket/first wall challenges and required R&D on the pathway to DEMO[J]. Fusion Eng. Des., 2015, 100: 2–43.
[2] Raffray A R, Calcagno B, Chappuis P, et al. Contributors from the blanket integrated product team, the ITER blanket system design challenge[J]. Nucl. Fusion, 2014, 54: 033004.
[3] Laffont G, Li A. Design approach for the main ITER test blanket modules for the EU helium cooled lithium-lead blankets[J]. Fusion Eng. Des., 2006, 81: 695–700.
[4] Malang S, Tillack M, Wong C, et al. Development of the lead lithium (DCLL) blanket concept[J]. Fusion Sci. Techn. 2011, 60: 249–256.
[5] Malang S, Raffray A R, Money N B. An example pathway to a fusion power plant system based on lead-lithium breeder: Comparison of the dual-coolant lead-lithium (DCLL) blanket with the helium-cooled lead-lithium (HCLL) concept as initial step[J]. Fusion Eng. Des., 2009, 12: 2145–2157.
[6] 汪卫华，刘松林. 聚变发电反应堆双冷铿铅包层热工水力学设计与分析[J]. 核科学与工程, 2005, 25(2): 163–168.
[7] Wu Y. Design analysis of the China dual-functional lithium lead DFLL test module in ITER[J]. Fusion Eng. Des., 2007, 82: 1893–1903.
[8] Abdou M A, Tillack M, Raffray A R. Thermal, fluid flow, and tritium release problems in fusion blankets[J]. Fusion Techn., 2009, 18(2): 165–200.
[9] Desheng Cheng, Weihua Wang, Haifei Deng, et al. Numerical investigation of channel for helium cooled China HCCB-TBM first wall by application enhance heat transfer method[J]. Journal of Fusion Energy, 2016, 35(5): 748–757.
[10] Haifei Deng, Desheng Cheng, Weihua Wang, et al. The cooling performance improvement of first wall using He/CO2 binary mixtures gas for CN HCCB TBM[J]. Fusion Sci. Techn., 2017, 72: 188–198.
[11] Baoguo Pan, Weihua Wang, Delin Chu, et al. Experimental investigation of hypervapotron heat transfer enhancement with alumina–water nanofluids[J]. International Journal of Heat and Mass Transfer, 2016, 98: 738–745.
[12] Bae Y D, Kim S K, Shin H Y, et al. Heat flux tests of the ITER first wall qualification mockups at KOHLT-1[J]. Fusion Eng. Des., 2011, 86: 412–416.
[13] Haifei Deng, Weihua Wang, Desheng Cheng, et al. Design and analysis of “filling-evacuating” highpressure helium-cooled loop[J]. IEEE Transactions on Plasma Science, 2018, 46: 412–419.
[14] Desheng Cheng, Weihua Wang, Haifei Deng, et al. The numerical simulation for the heat transfer enhancement experiments of the HCCB-TBM first wall[J]. IEEE Transactions on Plasma Science, 2018, 46: 1458–1465.

聚变堆液态包层增殖区铅锂与氦气多流场耦合换热特性研究

Coupled heat transfer characteristics study of multi-flow field between lead lithium and helium gas for liquid blanket breeder zone of fusion reactor

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