Telescopic control rod for significant reduction in HTR height and cost

2022 ◽  
Vol 169 ◽  
pp. 108953
Author(s):  
Ben Lindley ◽  
Peter Wilkinson ◽  
Adrien Couet ◽  
Farshid Shahrokhi
Keyword(s):  
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.


Author(s):  
Zhang Dan ◽  
Ran Xu ◽  
Qiu Zhifang ◽  
Zhou Ke ◽  
Feng Li

The method for ATWS (anticipated transient without scram) analysis was completely developed for commercial pressurized water (PWR) reactor plants, especially for selecting of typical initial events. For accident analysis of ATWS, it is different between PWR and small modular reactor (SMR), as different structures and characters, and it is necessary to study the typical initial events for these reactors. Based on the standard of PWR, the demanding for ATWS analysis was studied and the consequences for typical anticipated transient was calculated using RELAP5/MOD3.2 code, “maintain reactor coolant pressure boundary integrity” was selected as limiting criterion. The results shows for SMR, anticipated transient with the most serious consequence for ATWS are loss of offsite power and inadvertent control rod withdraw event, this conclusion will support to prepare the safety analysis report and optimum design of diversity activation system (DAS) for SMR.


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