scholarly journals The simulation of start-up of natural circulation boiler based on the Astrom-Bell model

2017 ◽  
Author(s):  
Tianyu Zhang ◽  
Zhenning Zhao ◽  
Yuanyuan Li ◽  
Xianran Zhu
Energy ◽  
2015 ◽  
Vol 92 ◽  
pp. 153-159 ◽  
Author(s):  
Jan Taler ◽  
Bohdan Węglowski ◽  
Dawid Taler ◽  
Tomasz Sobota ◽  
Piotr Dzierwa ◽  
...  

Author(s):  
R. K. Bagul ◽  
D. S. Pilkhwal ◽  
P. K. Vijayan ◽  
D. Saha

Natural circulation is being adopted as a mode of core heat removal in several nuclear reactors that are under development. This is due to the passive nature of natural circulation that enhances the system safety and reliability. However, major concern in the design of natural circulation based reactor systems is to avoid the flow instabilities that may occur under certain operating conditions, i.e. unstable operational regime. Therefore various reactor operational transients such as start-up, power raising, setback and also the steady state operating points must fall within the stable regime. The choice of operating procedures needs to be made judiciously and which also needs to be validated and supported by experiments. Advanced Heavy Water Reactor (AHWR) being developed in India is a pressure tube type natural circulation boiling water-cooled reactor, wherein major part of the power is generated by thorium. Experiments and analytical studies have been performed to arrive at a rational start-up procedure for AHWR. Experimental results obtained in simple rectangular natural circulation loops as well as in a scaled down facility have revealed the importance of external pressurization to avoid the flashing and Type-I instabilities that occur at low pressure during start-up.


1993 ◽  
Vol 59 (565) ◽  
pp. 2621-2627
Author(s):  
Masanori Aritomi ◽  
Hsien Jing Chiang ◽  
Michitsugu Mori ◽  
Masahisa Higuchi
Keyword(s):  

1992 ◽  
Vol 29 (7) ◽  
pp. 631-641 ◽  
Author(s):  
Masanori ARITOMI ◽  
Jing Hsien CHIANG ◽  
Tohru NAKAHASHI ◽  
Masumi WATARU ◽  
Michitsugu MORI

Author(s):  
Fumiaki Yamada ◽  
Hiroaki Ohira

Flow network models of the upper plenum of reactor vessel and the primary inlet plenum of intermediate heat exchanger (IHX) of MONJU were advanced and each model was validated by the measured data obtained in the previous system start-up tests (SSTs). Then the whole plant dynamics in a plant trip transient of MONJU were simulated by incorporating these flow network models. The natural circulation in the primary and secondary heat transport systems were also validated by these test results. From these validations, we concluded that the plant dynamics model incorporated the advanced models in Super-COPD code could simulate the whole plant dynamics in good accuracy both in the transients and natural circulation conditions and that it was applicable to predict the next SSTs.


2013 ◽  
Vol 265 ◽  
pp. 1131-1147 ◽  
Author(s):  
Abhinav Dixit ◽  
Takashi Hibiki ◽  
Mamoru Ishii ◽  
Kouichi Tanimoto ◽  
Yoshiyuki Kondoh ◽  
...  

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