Software verification process and methodology for the development of FPGA-based engineered safety features system
- 1. Center for Nuclear Reactor Safety and Technology, National Nuclear Energy Agency of Indonesia (BATAN), Kawasan Puspiptek Serpong Gd.80, Setu, Tangerang Selatan, Banten 15310 (Indonesia)
- 2. Department of Nuclear Power Plant Engineering, KINGS Instrumentation and Control Lab, KEPCO International Nuclear Graduate School, 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 45014 (Korea, Republic of)
Description
Highlights: • Verification methods for safety critical I&C system nuclear power plant. • Verification methods by following system engineering approach based software design life cycle. • Adopt verification by testing methods for VHDL code, refers to standards related to I&C system, FPGA and HDL Language. • Verified FPGA-based system for safety I&C system in nuclear power plant. - Abstract: Verification process is very important for the new development or re-engineering process for Instrumentation and Control (I&C) in Nuclear Power Plant (NPP). Due to the fact that the Engineered Safety Feature-Component Control System (ESF-CCS) is safety critical system, it is necessary to specify a systematic approach to verify the performance of development design. For this verification process, a system engineering approach is used and refers to the software design life cycle to verify the VHDL code in the implementation of Field Programmable Gate Array (FPGA)-based ESF-CCS. Although FPGA does not use software, however, FPGA needs a Hardware Description Language (HDL) to describe digital and mixed-signal for an integrated system. Therefore, the VHDL code should be verified to make sure that this code level will not cause an error for the FPGA-based system, especially for ESF-CCS development. The verification method is started by looking at the requirements analysis, verification of the outputs of the design by develop software testing to verify the reliability of the code which is to support the FPGA-based ESF-CCS. White Box testing is used for software testing to demonstrate the responds from the VHDL code, whether the design is success or not, and the coverage test is at 100% coverage state. In addition, the Static Timing Analysis (STA) is applied to check the delay time. Once all verification steps have been performed, then the results of the design can be validated. In this paper, FPGA-based ESF-CCS using VHDL code is verified.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2018.02.009Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2018.02.009;
- PII
- S0029549318300840;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 330
- Journal Page Range
- p. 325-331
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50082088
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPUTER CODES; CONTROL SYSTEMS; DESIGN; LIFE CYCLE; NUCLEAR POWER PLANTS; SAFETY; TESTING; TIME DELAY; VERIFICATION
- Descriptors DEC
- NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.