Diversity and defense-in-depth analysis for I and C systems of research reactors: A case study on two research reactors - 376
Creators
- 1. Division of Research Reactor System Design Korea Atomic Energy Research Institute 111, Daedeok-daero 989beon-gil, Yuseong-gu, Daejeon (Korea, Republic of)
Description
This paper provides the analysis results of the diversity and defense-in-depth (D3) applied to two research reactors designed by the Korea Atomic Energy Research Institute. The D3 assessments for instrumentation and control (I and C) systems of two research reactors are performed according to the guidelines documented in NUREG/CR-6303. The I and C systems are classified into four echelons of defense: control echelon, reactor trip echelon, engineered safety feature (ESF) actuation echelon, and monitoring and indication echelon. The diversity between the echelons of defense is assessed to determine that a single software common cause failure (CCF) does not impair the functions of multiple echelons of defense. In addition, the effects of a software CCF of the reactor protection system on the design basis events of the research reactors are analyzed by assuming that the automated reactor trip and ESF actuation functions of the reactor protection system are inoperable due to the software CCF. From the D3 analyses for the research reactors, it is verified that (1) adequate diversity has been provided, (2) adequate defense-in-depth has been provided, and (3) the displays and manual controls for critical safety functions initiated by operator action are diverse from digital systems used in the automatic portion of the protection system. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 10 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075836
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; DIGITAL SYSTEMS; NUCLEAR ENERGY; REACTOR CONTROL SYSTEMS; REACTOR DESIGN; REACTOR INSTRUMENTATION; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; RECOMMENDATIONS; RESEARCH REACTORS
- Descriptors DEC
- CONTROL SYSTEMS; DESIGN; ENERGY; ENGINEERED SAFETY SYSTEMS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; SAFETY
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)