Data concentrator requirements for a safety parameter display system

Journal Article · Mon Jan 31 23:00:00 EST 1983 · IEEE Trans. Nucl. Sci.; (United States)

DOI:https://doi.org/10.1109/TNS.1983.4332371· OSTI ID:5953508

Brewer, C R

To comply with NUREG 0696 several nuclear plants are being fitted with new facilities and data systems; specifically a Technical Support Center (TSC), Operational Support Center (OSC), Emergency Operational Facility (EOF), and Backup Safety Parameter Display System (SPDS), Emergency Response Computer System (ERCS) and Nuclear Data Link (NDL). The TSC, OSC, and EOF are physical locations while the SPDS, ERCS, and NDL are Systems. The SPDS and ERCS are usually separate and independent systems, however, they may share a common front end data acquisition system that acquires and sends SPDS related data to both the SPDS and to the ERCS. In the situation just described an SPDS system must depend upon input data from a source that is SPDS host computer independent. To achieve this independence the front end data acquisition system may employ a concept of intelligent distributed processing. This concept essentially takes functional capabilities that were once found only in realtime host computers and distributes it to front end data acquisition systems. Thus by expanding the functionality of the data acquisition system in a manner that provides more capability, independence from the computer vendor, links to multiple computer systems, processing power and redundancy, the concept of a data concentrator evolved. This paper will define this new distributed functionality, and its related requirements. It will also examine different system configuration approaches.

• Research Organization: SGM, INC 1001 N.W. 62nd St., Suite 300p, Ft. Lauderdale, FL 33309
• OSTI ID: 5953508
• Journal Information: IEEE Trans. Nucl. Sci.; (United States), Journal Name: IEEE Trans. Nucl. Sci.; (United States) Vol. 30:1; ISSN IETNA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTERS
CONTROL SYSTEMS
DATA ACQUISITION SYSTEMS
DATA PROCESSING
DISPLAY DEVICES
DISTRIBUTED DATA PROCESSING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROCESSING
RADIATION PROTECTION
REACTOR CONTROL SYSTEMS
REACTOR SAFETY
REGULATIONS
RETROFITTING
SAFETY
THERMAL POWER PLANTS