Published April 2018 | Version v1
Journal article

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.2018.02.009

Additional 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.