Uncontrolled withdrawal of a control rod without SCRAM

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

Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO

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

The role of separation on the forces acting on a circular cylinder with a control rod

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

Abstract

Fuel Cycle Extension by Part-Length Control Rod Removal at Rancho Seco

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

Preliminary Design of Unloading Device for MNSR LEU Conversion

2018 ◽  
Author(s):  
Hao Qian ◽  
Li Yiguo ◽  
Peng Dan ◽  
Wu Xiaobo ◽  
Lu Jin ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Reactor Vessel ◽  
Cover Plate ◽  
Spent Fuel ◽  
Long Distance ◽  
Control Rod ◽  
Small Cover ◽  
Sealing Performance ◽  
Safety And Reliability ◽  
Application Requirements

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.

Study on Typical Initial Event of ATWS for Small Modular Reactor

2016 ◽  
Author(s):  
Zhang Dan ◽  
Ran Xu ◽  
Qiu Zhifang ◽  
Zhou Ke ◽  
Feng Li
Keyword(s):  
Optimum Design ◽  
Safety Analysis ◽  
Accident Analysis ◽  
Pressurized Water ◽  
Control Rod ◽  
Reactor Coolant ◽  
Initial Event ◽  
Small Modular Reactor ◽  
Activation System

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.

Implementation of control rod movement and boron injection options by using control variables in RELAP5/PARCS V2.7 coupled code

2011 ◽  
Vol 53 (8) ◽  
pp. 1084-1090 ◽  
Author(s):  
R. Miró ◽  
T. Barrachina ◽  
A. Abarca ◽  
G. Verdú ◽  
C. Pereira ◽  
...  
Keyword(s):  
Control Variables ◽  
Control Rod
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