Published 1994 | Version v1
Report Open

Application-specific integrated circuit design for a typical pressurized water reactor pressure channel trip

Creators

  • 1. Oak Ridge National Lab., TN (United States)
  • 2. Electric Power Research Inst., Palo Alto, CA (United States)

Description

This article discusses the use of application-specific integrated circuits (ASICs) in nuclear plant safety systems. ASICs have certain advantages over software-based systems because they can be simple enough to be thoroughly tested, and they can be tailored to replace existing equipment. An architecture to replace a pressurized water reactor pressure channel trip is presented. Methods of implementing digital algorithms are also discussed

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE94007207; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
10 p.
Report number
CONF-9406126--1

Conference

Title
1994 joint Instrument Society of America and Electric Power Research Institute conference.
Dates
5-8 Jun 1994.
Place
Orlando, FL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058745
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; DESIGN; DIGITAL CIRCUITS; DIGITAL FILTERS; ELECTRICAL TESTING; ELECTRONIC EQUIPMENT; ENGINEERED SAFETY SYSTEMS; INTEGRATED CIRCUITS; PWR TYPE REACTORS; REACTOR CHANNELS
Descriptors DEC
ELECTRONIC CIRCUITS; ENRICHED URANIUM REACTORS; EQUIPMENT; MATERIALS TESTING; NONDESTRUCTIVE TESTING; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
USDOE, Washington, DC (United States).