Software verification process and methodology for the development of FPGA-based engineered safety features system

Maerani, Restu; Mayaka, Joyce; Jung, Jae Cheon

doi:10.1016/j.nucengdes.2018.02.009

Cited by 13 publications

(5 citation statements)

References 6 publications

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“…Studi terkait implementasi FPGA pada reaktor nuklir sudah dilakukan sebelumnya pada desain SPR dan Engineered Safety Features -Component Control System (ESF -CCS) untuk reaktor daya tipe APR1400 [3,4].…”

Section: Pendahuluanunclassified

“…Alasan penggunaan FPGA juga dikarenakan pada pengujian di ESF -CCF berbasis perangkat keras (FPGA) terbukti lebih mudah dan dapat terpenuhi 100% coverage analisis fungsinya, mengingat pada desain perangkat lunak umumnya banyak terjadi kegagalan [4,5]. FPGA juga dinyatakan mampu mengurangi kompleksitas sistem jika dibandingkan dengan sistem berbasis PLC, yaitu dengan perancangan berbasis perangkat keras untuk menggantikan elektronik analog pada hasil desain akhirnya [6].…”

Section: Pendahuluanunclassified

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Kajian Implementasi Field Programmable Gate Array untuk Rencana Modernisasi Sistem Proteksi Reaktor

Maerani

Suryono

Santoso

et al. 2020

Jurnal Pengembangan Energi Nuklir

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Penggunaan Field Programmable Gate Array (FPGA) pada reaktor nuklir sudah dilakukan sejak 2016, terutama diaplikasikan pada perangkat Sistem Instrumentasi dan Kendali (SIK). FPGA sebelumnya sudah diujikan pada rancangan Sistem Proteksi Reaktor (SPR) dan Engineered Safety Feature – Component Control System (ESF-CCS) reaktor daya tipe APR1400. Dengan adanya rencana peremajaan SIK reaktor serbaguna G.A. Siwabessy (RSG-GAS) pada bagian SPR, diharapkan sistem berbasis FPGA juga dapat diimplementasikan pada reaktor riset. Dengan pertimbangan nilai ekonomi, keamanan dan juga keandalannya, FPGA yang berbasis perangkat keras dinilai akan lebih aman dari serangan jaringan, lebih murah dari Programmable Logic Controller (PLC) yang berbasis perangkat lunak dan proses verifikasi dan validasinya yang lebih sederhana. Untuk menjamin berlangsungnya performa SPR RSG-GAS, proses digitalisasi perangkat kendali tidak dapat dihindari dan sebaiknya dilakukan. Penelitian ini membahas siklus perancangan berbasis FPGA yang diawali dengan mengkaji dokumen panduan terkait sistem yang penting untuk keselamatan terutama yang berbasis FPGA agar dapat mengacu kepada persyaratan, baik untuk perancangan perangkat keras maupun perangkat lunak, proses reverse engineering hingga proses validasi. Hasil dari penelitian ini bertujuan agar pada proses desain dalam upaya peremajaan SPR RSG-GAS dapat mengikuti metode yang telah disyaratkan terkait perancangan SIK berbasis FPGA untuk reaktor riset, sehingga dapat mempermudah proses perolehan ijin dari badan pengawas tenaga nuklir untuk dapat dilakukan penggantian desain SPR berbasis FPGA.

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Section: Pendahuluanunclassified

Kajian Implementasi Field Programmable Gate Array untuk Rencana Modernisasi Sistem Proteksi Reaktor

Maerani

Suryono

Santoso

et al. 2020

Jurnal Pengembangan Energi Nuklir

Self Cite

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“…The adoption of FPGA technology (previous paragraph) may represent a solution. However, although FPGA does not use software, it needs a specific 'Hardware Description Language': this again needs verification, Maerani et al 2018, see also Ahmed et al 2017, andKang et al 2018.…”

Section: Software Reliability (And Verification)mentioning

confidence: 99%

The technological challenge for current generation nuclear reactors

D'Auria¹,

Debrecin²,

Glaeser³

2019

NUCET

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The present paper deals with the proposal of an additional safety barrier for the class of large (1000 MWe or more) Light Water Reactors (LWR) now in operation, in construction, or under design. Emphasis is given to the motivations or the needs for the barrier. Two main parts of the paper can be distinguished. The following topics are discussed in the former part (section 2): (a) the weakness of the barrier constituted by the current design of nuclear fuel; (b) the continuously increasing complexity of the system, with main reference to the Instrumentation and Control (I&C); (c) the role that the Large Break Loss of Coolant Accident (LBLOCA) had for arriving at the current layout of the Reactor Coolant System (RCS). Furthermore avoiding the severe accidents in 1979, 1987 and 2011, is at the basis of the proposal. In the latter part (sections 3 and 4), the elements of the proposed technological safety barrier are discussed: the As-Low-As-Reasonably-Achievable (ALARA) principle, the Best Estimate Plus Uncertainty (BEPU) approach, the Extended Safety Margin Detection (E-SMD) hardware, the Emergency Rescue Team (ERT) strategy (or a virtual entity for the reactor) and the Independent Assessment (IA) concept. The additional safety barrier, although not demonstrated in the paper, is expected to reduce for a factor in the range 10–1000 the probability of core melt and to have a cost in the order of 1% the cost of a nuclear reactor unit.

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“…Devido aos problemas relacionados ao licenciamento de software, muitos projetos de sistemas digitais de I&C têm considerado a aplicação de dispositivos programáveis por linguagem de hardware (HDL -Hardware Description Language). Uma família de componentes que tem sido utilizada nos projetos e utilizam a linguagem HDL são os FPGA's (Field Programmable Gate Array) (Farias et al, 2016;Maerani, Mayaka & Jung, 2018). Alguns pontos ainda precisam ser avaliados para introdução desses dispositivos em sistemas de usinas nucleares como: banco de dados de confiabilidade, experiência operacional, definição de requisitos, adoção das funcionalidades já testadas, existência de um número reduzido de fornecedores qualificados para a área nuclear, dificuldades relacionadas à aplicação de métodos de codificação e desenvolvimento de ferramentas para validação (IAEA, 2012).…”

Section: Impacto Da Linguagem De Configuração De Hardware Em Dispositunclassified

Os Desafios Do Licenciamento De Sistemas Digitais De Instrumentação E Controle Em Usinas Nucleares

Vital

2019

R. Eletr. TECCEN

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ResumoOs processos de obsolescência e desenvolvimento de novos projetos de usinas nucleares demandam por equipamentos/ componentes de Instrumentação e Controle (I&C) com melhor desempenho atendendo a requisitos de segurança cada vez mais rígidos. Em função dessa demanda, a aplicação de sistemas digitais de I&C apresenta-se como uma boa solução tecnológica, mas precisa ser validada por processos específicos de licenciamento. Diante da importância do assunto e da demanda existente, este artigo apresenta algumas atividades que tem sido realizadas para atender aos requisitos e recomendações de diversos reguladores do setor nuclear. Dessa forma, são mostrados os pontos de maior questionamento regulador e experiências sobre o processo de licenciamento de sistemas digitais de I&C em diferentes culturas reguladoras. Palavras-Chave: Usina Nuclear, Licenciamento, Instrumentação e Controle.Tatiane Melo Vital †* , Richard Brandão Nogueira Vital † The challenges of licensing of digital instrmentation and control system in Nuclear Power plants Os desafios do licenciamento de sistemas digitais de instrumentação e controle em Usinas Nucleares AbstractObsolescence process and new nuclear power plant designs demands instrumentation and control equipment and components with better performance and it shall attend stronger safety requirements. To attend this demand, the application of digital I&C appears like a good technologic solution but shall be validated by specific licensing processes. Due the importance and demand of this subject, this paper shows some activities that had been executed to attend requirements and recommendations of nuclear regulators. This work presents the highlights and experiences of digital I&C licensing in different regulator culture.

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Software verification process and methodology for the development of FPGA-based engineered safety features system

Cited by 13 publications

References 6 publications

Kajian Implementasi Field Programmable Gate Array untuk Rencana Modernisasi Sistem Proteksi Reaktor

Kajian Implementasi Field Programmable Gate Array untuk Rencana Modernisasi Sistem Proteksi Reaktor

The technological challenge for current generation nuclear reactors

Os Desafios Do Licenciamento De Sistemas Digitais De Instrumentação E Controle Em Usinas Nucleares

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