Integration of CATHENA Thermal-Hydraulic Model with CANDU 6 Analytical Simulator Controller
Integration of CATHENA Thermal-Hydraulic Model with CANDU 6 Analytical Simulator Controller
摘要
This paper introduces a powerful design and analysis tool named SIMCAT, that is developed to support applications to license a CANDU nuclear reactor, refurbish projects, and support the existing CANDU stations. It consists of the CATHENA (Canadian Algorithm for Thermo-Hydraulic Network Analysis), the control logics from C6SIM (CANDU 6 Analytical Simulator), and a communication protocol, PVM (parallel virtual machine). This is the first time that CATHENA has been successfully coupled directly with a program written in another language. The independence of CATHENA and the C6SIM controllers allows the development of both CATHENA and C6SIM controller to proceed independently.
参考文献9
-
1B.N. Hanna, CATHENA: A thermal-hydraulic code for CANDU analysis, Nuclear Engineering and Design 180 (1998) 113-131.
-
2Quality Assurance of Analytical, Scientific and Design Computer Programs for Nuclear Power Plants, CSA N286.7-99, 1999.
-
3A Themal-Hydraulic System Simulation Model for the Reactor, Boiler, and Heat Transport System (SOPHT), Ontario Hydro CNS-00037-002, Sept. 1997.
-
4M. Borairi, J. Tseng, Y. Zhao, Dynamic simulation of CANDU 6 reactor, in: Symposium on Simulation Methods in Nuclear Engineering, Ottawa, Canada, Nov. 2008.
-
5H. Javidnia, J. Jiang, M. Borairi, Modeling and simulation of CANDU reactor control system, International Journal of Nuclear Technology 165 (2008) 174-178.
-
6M. Borairi, Developing shutdown system reliability test profiles using simulation based approach, in: 3rd Workshop on the Application of FPGAs in Nuclear Power Plants, Hamilton, Canada, Sept. 2010.
-
7B. Hanna, CATHENA MOD-3.5d Validation Plan, AECL report COG-01-204, March 2003.
-
8Getting Started with Simulink Coder, the MathWorks Inc., Sept. 2011.
-
9A. Geist, A. Beguelin, J. Dongarra, W.C. Jiang, R. Manchek, V.S. Sunderam, PVM: A User's Guide and Tutorial for Networked Parallel Computing, MIT Press, USA, 1994.
-
1冯进军.CANDU反应堆物理数值计算技术[J].中国核工业,2010(6):42-46.
-
2戴正熙,陈可,张琴舜,沈秀中,蔡日基,陈培培,刘洋,邹文进.CANDU9蒸汽发生器仿真[J].现代机械,2001(4):20-24.
-
3田野,贾宝山,阎林.TACR非能动慢化剂余热排出系统消除不稳定性研究[J].核动力工程,2010,31(3):40-44.
-
4Aman Usmani,Zane Walker.Overview and Lessons from More Than a Decade of Feeder Life Management[J].Journal of Energy and Power Engineering,2013,7(11):2164-2173.
-
5朱鑫官,蔡剑平,HankChow.CANDU反应堆物理程序和方法[J].核动力工程,1999,20(6):538-542. 被引量:3
-
6闫林,贾宝山,廉海波.全厂断电事故时TACR-1000非能动慢化剂余热排出系统排热能力研究[J].核动力工程,2008,29(4):117-122. 被引量:2
-
7吴巍.三维模型化设计浏览软件的特点及其工程应用[J].化工设计,2002,12(6):29-34.
-
8郑华,臧希年.非能动安注箱的设计与分析[J].核科学与工程,2005,25(2):149-153. 被引量:3
-
9M.Saldideh,M.Shayesteh,M.Eshghi.Neutronic calculations for CANDU thorium systems using Monte Carlo techniques[J].Chinese Physics C,2014,38(8):111-115.
-
10贾红轶,杨萍.QM-400模块隔热板敏感性分析[J].核科学与工程,2013,33(3):245-249. 被引量:3