Nuclear facilities. Instrumentation and control systems. Design, location and application criteria for installed area gamma radiation dose rate monitoring equipment for use during normal operation and anticipated operational occurrences

2020 ◽  
Author(s):  
Muhammad Shahzaib Atif ◽  
Zarrar Haider ◽  
Malik Muhammad Zohaib ◽  
Mirza Ali Raza

Author(s):  
Francesco Cordella ◽  
Mauro Cappelli ◽  
Massimo Sepielli

In control systems design for nuclear facilities, the correct choice for sensors, transducers and actuators is not an easy task when different options must be evaluated. In particular, for a Once Through Steam Generator (OTSG), the control of its boiling flow dynamics is usually performed with sensors that may be slow in response, must be placed all through the zone of interest (or need heavy mechanical modifications) and may not distinguish correctly when the liquid/steam interface is not so well defined at high temperatures and pressures. In this paper, a theoretical study about a reflectometric technique applied to an OTSG is proposed. This technique can be used also for the liquid/steam levels monitoring of the boiling flow. The overall behaviour of the variables of interest and the first theoretical results show the benefits of such an innovative approach.


Nukleonika ◽  
2014 ◽  
Vol 59 (2) ◽  
pp. 67-72 ◽  
Author(s):  
Farahnaz Saadatian-derakhshandeh ◽  
Omid Safarzadeh ◽  
Amir Saiid Shirani

Abstract One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed a justifiable approach called D4D4 to estimate the control rod worth of a VVER-1000 reactor that enables to perform the best estimate analysis and reduce the conservatism that utilize DRAGON4 and DONJON4. The results are compared with WIMS-D4/CITATION to show the effectiveness and superiority of the developed package in predicting reactivity worth of the rod and also other reactor physics parameters of the VVER-1000 reactor. The results of this study are in good agreement with the plant's FSAR.


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