Silver-Indium-Cadmium Control Rod Behavior in Severe Reactor Accidents

1989 ◽  
Vol 84 (2) ◽  
pp. 128-151 ◽  
Author(s):  
David A. Petti
Author(s):  
Zuokang Lin ◽  
Lin Zhu ◽  
Chunfeng Zhao ◽  
Yun Cao ◽  
Xiao Wang

The reactor scram function realized by the rapidly dropping of control rods ensures safety when the reactor accidents (loss of electricity and earthquake, etc.) happen. In the thorium base molten salt reactor (TMSR - SF1), the rod drop time is obviously affected by the resistance which produced in the molten salt as its high density and viscosity. In this paper, the drop time of the control rod is obtained by the theoretical and experimental methods for comparison. Firstly, the drop time is analyzed both in air and water condition with calculation and experiment. And the method used for the resistance calculation of the rod during dropping is verified. Secondly, the similarity criterion is adopted to calculate the drop time in molten salt condition. The study shows that: 1) In air and water condition, the calculation is coincidence with the experimental results within the maximum error less than 2 %. 2) The drop time of the rod in molten salt is 2.8 s with a dropping height 2.4m in reactor, which satisfy the safety requirement of the control system. 3) It is necessary to use another buffer beside the disc spring to protect the driving mechanism of the rod during the rod dropping.


Kerntechnik ◽  
2016 ◽  
Vol 81 (4) ◽  
pp. 445-451
Author(s):  
F. Čajko ◽  
M. Sečanský ◽  
T. Chrebet ◽  
R. Zajac ◽  
P. Dařílek

Kerntechnik ◽  
2007 ◽  
Vol 72 (5-6) ◽  
pp. 262-267
Author(s):  
T. Abou-El-Maaty
Keyword(s):  

2021 ◽  
Vol 915 ◽  
Author(s):  
M.M. Cicolin ◽  
O.R.H. Buxton ◽  
G.R.S. Assi ◽  
P.W. Bearman

Abstract


1981 ◽  
Vol 55 (3) ◽  
pp. 583-586
Author(s):  
T. N. Ake ◽  
R. G. McAndrew ◽  
D. D. Whitney
Keyword(s):  

Author(s):  
Hao Qian ◽  
Li Yiguo ◽  
Peng Dan ◽  
Wu Xiaobo ◽  
Lu Jin ◽  
...  

In order to solve the problem that the current unloading operation will destroy the sealing performance of Miniature Neutron Source Reactor (MNSR) reactor vessel and the tightness can’t be restored, and to meet the application requirements that the original reactor vessel will be reloaded and operated after MNSR LEU conversion, the new unloading device is designed, which can be used without separation of reactor vessel. There has only one fuel assembly in MNSR. When the fuel assembly are unload for MNSR LEU conversion, the cover plate of the pool is removed, the cadmium string is put in, and the neutron detector is placed at first. After removing the drive mechanism and the control rod, and opening the small cover plate at the top of reactor vessel, the fuel assembly can be grabbed and unloaded by unloading tool only through the opening of the small top cover plate. The MNSR spent fuel has very high radioactivity. The auxiliary mechanical device can be used with unloading tools to realize operation in a long distance by lifting and level motion, which is convenient to shield and can reduce the works’ irradiation dose level effectively. Through calculation and analysis, the results show that the structure strength of unloading device is much larger than the actual load to ensure operation safety and reliability. The unloading device is easy to process and operate, and can be used in the practical operation of MNSR LEU conversion or decommissioning at home and abroad to simplify the operation steps and improve the working efficiency.


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