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Development process of FPGA based technology for control rod drive systems of experimental power reactor.

Authors :
Santoso, Sigit
Jojok Suryono, Tulis
Maerani, Restu
Deswandri
Fitri Atmoko, Dian
Manurung, Auralius
Source :
Nuclear Engineering & Design. Nov2022, Vol. 398, pN.PAG-N.PAG. 1p.
Publication Year :
2022

Abstract

• The V Model of system engineering was used in developing a Control Rod Drive System. • FPGA based CRDS is designed for Experimental Power Reactor, RDE. • Verification of the CRDS design requirements and related criteria/standard. • Prototype simulation for validating the logic function in FPGA based system. The Experimental Power Reactor (EPR) design was developed in Indonesia based on HTGR technology and employed fully-digitized system for reactor instrumentation and control. The field programmable gate array (FPGA) technology which has advantages in minimizing a common cause failure and vulnerability from the cyber- attack was employed in the design of control rod drive system (CRDS) of EPR. This paper discusses the process in developing of FPGA-based CRDS for EPR using the V-Model approach. Verification and adjustment were conducted toward the CRDS design requirement established in the preliminary research based on relevant design criteria, standard, and most recent data. The rule checking method has been used to verify that specified rules and criterias have been adhered. In this study a simulation prototype was designed and implemented into Digilent Basys3 FPGA board in order to conduct a thorough design verification and validation process. The results showed the conformity of system requirements with the corresponding standard and design criteria. In addition, the use of simulation prototypes will be beneficial for verification process and tends to increase the effectiveness of V-model in the development of control system for CRDS. The approach used in this study can be applied to designing other FPGA-based systems of EPR. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
00295493
Volume :
398
Database :
Academic Search Index
Journal :
Nuclear Engineering & Design
Publication Type :
Academic Journal
Accession number :
159708382
Full Text :
https://doi.org/10.1016/j.nucengdes.2022.111957