scholarly journals Hydraulic transient simulation of primary cooling circuit in Egyptian second research reactor

Author(s):  
Hesham Elkhatib ◽  
Adel Alyan ◽  
Adel Abdelrahman
2012 ◽  
Vol 41 ◽  
pp. 40-47 ◽  
Author(s):  
N.H. Badrun ◽  
M.H. Altaf ◽  
M.J.H. Khan ◽  
M.S. Mahmood ◽  
M.A. Motalab ◽  
...  

2019 ◽  
Vol 34 (2) ◽  
pp. 107-121
Author(s):  
Vitaly Uzikov ◽  
Irina Uzikova

This paper presents the results of an analysis of a universal cooling system for the core of re- search reactors built on the passive principle of natural convection. A 3-D model, technologi- cal and design diagrams of the reactor installation are provided, along with examples of nu- merical evaluation of transients during the operation of the cooling circuit in normal and emergency modes to substantiate the possibility of using such a cooling system in research re- actors of small and medium power. The principal feature of the described passive system is the absence of not only active elements, such as circulation pumps and shut-off and control valves from the cooling circuit, but also of passive elements with moving parts, such as a check valve. The cooling circuit includes only vessels, piping and a heat exchanger. The absence of elements with mechanical moving parts can significantly reduce the likelihood of equipment failures and improve the reliability of such a cooling system while also reducing its cost. The versatility of the proposed system allows it to be used for a wide range of research reactor plants with various capacities, which are nowadays being developed designed to carry out programs in various areas of research and applied usages related to nuclear technologies.


Author(s):  
Rafał Drobnik ◽  
Andrzej Głowacki

In this work the replacement of the I&C connected with the four main pumps in a Polish research reactor called “Maria” is discussed. In particular, this paper focuses on the aspect of the whole system of pump parameters measurements (temperature, vibrations, power) and pump control system. The whole architecture of the I&C system (including power supply, redundancy of electrical and control system) will be showed. During the I&C replacement some problems arose, such as the change in the pump control system from analog to digital system; the link existing in the reactor part of the measurement made in analogue to a digital system, as part of the measurements, which were carried out in an old control system; the code for the PLC controller program dedicated exclusively to the requirements of control systems pumps. All of these problems will be discussed here, together with the proposed solutions. Moreover, I&C functional and operational tests carried out after the placement of the pumps will be described, such as loss of power and failure of one PLC controller.


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