Environmental testing of a prototypic digital safety channel, phase I: System design and test methodology
A microprocessor-based reactor trip channel has been assembled for environmental testing under an Instrumentation and Control (I&C) Qualification Program sponsored by the U.S. Nuclear Regulatory Commission. The goal of this program is to establish the technical basis for the qualification of advanced I&C systems. The trip channel implemented for this study employs technologies and digital subsystems representative of those proposed for use in some advanced light-water reactors (ALNWS) such as the Simplified Boiling Water Reactor (SBNW) and AP600. It is expected that these tests will reveal any potential system vulnerabilities for technologies representative of those proposed for use in ALNWS. The experimental channel will be purposely stressed considerably beyond what it is likely to experience in a normal nuclear power plant environment, so that the tests can uncover the worst-case failure modes (i.e., failures that are likely to prevent an entire trip system from performing its safety function when required to do so). Based on information obtained from this study, it may be possible to recommend tests that are likely to indicate the presence of such failure mechanisms. Such recommendations would be helpful in augmenting current qualification guidelines.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10121048
- Report Number(s):
- CONF-9410216-9; ON: DE95007382; TRN: 95:002589
- Resource Relation:
- Conference: 22. water reactor safety information meeting,Bethesda, MD (United States),24-26 Oct 1994; Other Information: PBD: [1995]
- Country of Publication:
- United States
- Language:
- English
Similar Records
Assessing environmental compatibility of new technologies for use in nuclear power plants
Environmental testing of an experimental digital safety channel
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR INSTRUMENTATION
TESTING
TECHNOLOGY ASSESSMENT
DIGITAL SYSTEMS
DESIGN
NUCLEAR POWER PLANTS
BWR TYPE REACTORS
210100
220400
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
CONTROL SYSTEMS