Study on the Evaluation and Simulation of Steady State Behavior and Reactor Safety Concept for Integral Pressurized Water Reactor

2011 ◽  
Vol 10 (5) ◽  
pp. 983-991 ◽  
Author(s):  
Salah Ud-Din Kha ◽  
Minjun Peng ◽  
Muhammad Zubair
1999 ◽  
Vol 187 (1) ◽  
pp. 25-32 ◽  
Author(s):  
J. Czech ◽  
J. Wirkner ◽  
M. Yvon ◽  
M. Serret ◽  
U. Krugmann ◽  
...  

Author(s):  
Junli Gou ◽  
Suizheng Qiu ◽  
Guanghui Su ◽  
Dounan Jia

Natural circulation potential is of great importance to the inherent safety of a nuclear reactor. This paper presents a theoretical investigation on the natural circulation characteristics of an integrated pressurized water reactor. Through numerically solved the one-dimensional model, the steady-state single phase conservative equations for the primary circuit and the steady-state two-phase drift-flux conservative equations for the secondary side of the once-through steam generator, the natural circulation characteristics are studied. Based on the preliminary calculation analysis, it is found that natural circulation mass flow rate is proportional to the exponential function of the power, and the value of the exponent is related to working conditions of the steam generator secondary side. The higher height difference between the core center and the steam generator center is favorable to the heat removal capacity of the natural circulation.


2014 ◽  
Vol 2014 ◽  
pp. 1-7
Author(s):  
Zhang Fan ◽  
Lu Dao-Gang ◽  
Sui Dan-Ting ◽  
Guo Chao ◽  
Yuan Bo

Chinese integrated pressurized water reactor (CIPWR) has compact configuration and high inherent safety, which is appropriate for nuclear power plants of small and medium scale. Heat balance model has been adopted widely in thermal power calibration of PWRs because of its advantage of accuracy. In this paper, a package based on FORTRAN language is developed and added into RELAP5 to calculate the heat loss value needed in heat balance analysis. The steady-state operation of CIPWR is modelled correctly by RELAP5. The heat loss of CIPWR is calculated by the package, and the comparison of the main values of parameters needed in the heat loss calculation between RELAP5 and the package has been done. It shows that the package has high calculation accuracy and can be applied in reactor design and monitoring.


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