Qualification of some electronic components
Description
Qualification of safety-related systems as implemented by IEEE 323-1974, IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations, requires that the impact of aging be assessed. Where aging is significant, artificial or natural, aging procedures are used to put the system in its end-of-life condition. However, for many components which are providing safety-related functions, aging is insignificant to the ability of the component to be able to perform its safety-related function. Some of the analyses which have been performed by Wyle Laboratories on specific electronic components are presented. The analyses include review of applicable military specification tests, manufacturers' tests, and other qualification programs
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Thermal reactor safety
- Journal Page Range
- p. 509-515.
- Report number
- CONF-800403--(Vol.1)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11571356
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ELECTRONIC EQUIPMENT; NUCLEAR POWER PLANTS; PERFORMANCE TESTING; PWR TYPE REACTORS; QUALITY ASSURANCE; SAFETY ENGINEERING
- Descriptors DEC
- NUCLEAR FACILITIES; POWER PLANTS; REACTORS; TESTING; THERMAL POWER PLANTS; WATER COOLED REACTORS; WATER MODERATED REACTORS