大型池式钠冷快堆紧急停堆瞬态主系统集成仿真

Integrated Simulation of Transient Main System for Emergency Shutdown of Large Pool-Type Sodium-Cooled Fast Reactor

摘要

基于国内仿真支撑平台vPower,建立大型钠冷快堆堆芯系统、一回路、二回路、三回路及主要仪控系统仿真模型,对大型池式钠冷快堆紧急停堆工况下主系统动态响应特性进行仿真分析,并将仿真计算结果与实堆试验数据进行对比验证.结果表明,在满功率稳态工况下,仿真计算结果与实堆运行数据偏差小于1%,紧急停堆瞬态下仿真计算结果与实堆数据符合较好,主要变量变化趋势基本一致,可准确反映反应堆主系统的动态特性.

Abstract

Based on the domestic simulation support platform vPower, we established a simulation model of the core system, primary circuit, secondary circuit, tertiary circuit and main instrumentation and control system of large sodium-cooled fast reactor. We simulated and analyzed the dynamic response characteristics of the main system under the emergency shutdown condition of a large pool-type sodium-cooled fast reactor, and compared and verified the simulation calculation results with the real reactor test data. The results show that the deviation between the simulation calculation results and the real reactor operation data under the full power steady-state condition is less than 1%, the simulation calculation results fit well with the real reactor data under the emergency shutdown transient state, and the change trend of the main variables is basically consistent, which can accurately reflect the dynamic characteristics of the main reactor system.

关键词

池式钠冷快堆 / 紧急停堆 / 全厂协调控制 / 仿真计算

Key words

pool-type sodium-cooled fast reactor / emergency shutdown / coordinated control of whole plant / simulation calculation

参考文献

[1] 徐銤. 发展快堆-保障我国核能可持续发展[J]. 中国核工业, 2008, 1(9):20-23.

[2] (XU M. Development of Fast Reactors to Ensure the Sustainable Development of Nuclear Energy in China[J]. China Nuclear Industry, 2008, 1(9): 20-23.)

[3] 张东辉, 王松平, 代智文, 等. 我国快堆的创新与发展[J]. 核科学与工程, 2024, 44(5):980-988.

[4] (ZHANG D H, WANG S P, DAI Z W, et al. Innovation and Development of Fast Reactors in China[J]. Nuclear Science and Engineering, 2024, 44(5): 980-988.)

[5] FLOYD E, PROHAMMER D F G. The SASSYS LMFBR Systems Analysis Code[J]. Mathematics and Computers in Simulation, 1984, 26(1): 23-26.

[6] KWON Y M, LEE Y B, CHANG W P, et al. Development of a System Code, SSC-K, for Inherent Safety Evaluation of the Korea Advanced Liquid Metal Reactor[J]. Journal of the Korean Nuclear Society, 2001, 33(2): 209-224.

[7] 王晋, 张东辉, 胡文军. 池式钠冷快堆系统分析程序开发[J]. 原子能科学技术, 2016, 50(2):198-203.

[8] (WANG J, ZHANG D H, HU W J. Development of System Analysis Code for Pool-Type Sodium-Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2016, 50(2): 198-203.)

[9] 王晓坤, 齐少璞, 杨军, 等. 钠冷快堆系统程序FR-Sdaso开发[J]. 原子能科学技术, 2020, 54(11):2045-2053.

[10] (WANG X K, QI S P, YANG J, et al. Development of System Code FR-Sdaso for Sodium-Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2020, 54(11): 2045-2053.)

[11] 陆道纲, 隋丹婷. 池式快堆系统瞬态分析软件开发[J]. 原子能科学技术, 2012, 46(5):542-548.

[12] (LU D G, SUI D T. Development of System Analysis Code for Pool-Type Fast Reactor under Transient Operation[J]. Atomic Energy Science and Technology, 2012, 46(5): 542-548.)

[13] 秋穗正, 张大林, 宋苹, 等. 钠冷快堆瞬态热工水力及安全分析程序开发[J]. 原子能科学技术, 2019, 53(10):1941-1951.

[14] (QIU S Z, ZHANG D L, SONG P, et al. Code Development for Transient Thermal-Hydraulics and Safety Analysis of Sodium-Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2019, 53(10): 1941-1951.)

[15] 北京诺思维信科技有限公司. vPower仿真系统技术白皮书[M]. 北京: 北京诺思维信科技有限公司, 2009:35-50.

[16] (Beijing Neoswise Technology Co., Ltd. vPower Simulation System Technical White Paper[M]. Beijing: Beijing Neoswise Technology Co., Ltd., 2009: 35-50.)

[17] 齐少璞, 杨红义, 杨晓燕, 等. 基于FR-Sdaso的法国凤凰堆寿期末自然循环实验分析[J]. 原子能科学技术, 2020, 54(2):273-280.

[18] (QI S P, YANG H Y, YANG X Y, et al. Analysis of French Phenix End-of-Life Natural Circulation Test Based on FR-Sdaso[J]. Atomic Energy Science and Technology, 2020, 54(2): 273-280.)

[19] 叶尚尚, 杨红义, 刘一哲, 等. 钠冷快堆二回路系统热工水力瞬态分析程序SELTAC的开发与应用[J]. 原子能科学技术, 2018, 52(6):1013-1020.

[20] (YE S S, YANG H Y, LIU Y Z, et al. Development and Application of Transient Analysis Code SELTAC for Secondary Loop of Sodium-Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2018, 52(6): 1013-1020.)

[21] 叶尚尚, 杨红义, 刘一哲, 等. 钠冷快堆直流式蒸汽发生器固定网格与滑移网格模型对比分析[J]. 原子能科学技术, 2017, 51(7):1219-1224.

[22] (YE S S, YANG H Y, LIU Y Z, et al. Comparative Analysis of Fixed Grid and Sliding Grid Models for Once-Through Steam Generator in Sodium-Cooled Fast Reactor[J]. Atomic Energy Science and Technology, 2017, 51(7): 1219-1224.)

[23] 吕崇德, 任挺进, 姜学智, 等. 大型火电机组系统仿真与建模[M]. 北京: 清华大学出版社, 2002:200-207.

[24] (LYU C D, REN T J, JIANG X Z, et al. Large-Scale Thermal Power Unit System Simulation and Modeling[M]. Beijing: Tsinghua University Press, 2002: 200-207.)

[25] 北京诺思维信科技有限公司. vPower一体化仿真建模环境用户手册[M]. 北京: 北京诺思维信科技有限公司, 2008:2-76.

[26] (Beijing Neoswise Technology Co., Ltd. vPower Integrated Simulation Modeling Environment User Manual[M]. Beijing: Beijing Neoswise Technology Co., Ltd., 2008: 2-76.)

基金资助

国家自然科学基金(12375165)