Published 1986 | Version v1
Journal article

Retrofit of new digital control systems in existing power stations

  • 1. Atomic Energy of Canada Ltd., Montreal, Quebec

Description

With the notable exception of the Canadian CANDU nuclear power stations, little use has been made of digital control in North American nuclear stations. Recently, however, there has been renewed interest in such systems within the nuclear industry in response to demands for better ergonomics in control room design and the obsolescence of control equipment whose fundamental design has changed little in 20 yr. Early in 1985, Atomic Energy of Canada Limited was asked by New Brunswick Power to advise on the redesign of the control systems for two fossil-fired generating stations, Coleson Cove and Courtenay Bay Unit 4. Coleson Cove is to be converted from oil to coal firing with consequent extensive control system changes and Courtenay Bay Unit 4 required a low-cost solution to the problem of relocating its control room from the existing isolated location to the combined control center used by units 1, 2, and 3. In both cases, the recommended solution involves the retrofit of state-of-the-art digital control systems. Although the units involved are nonnuclear the experience is applicable

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
52
Series
Trans. Am. Nucl. Soc.
Journal Page Range
608-609
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
15-20 Jun 1986.
Place
Reno, NV (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18080609
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; COMPUTERS; CONTROL ROOMS; CONTROL SYSTEMS; EDUCATION; FOSSIL-FUEL POWER PLANTS; PROGRAMMING; REACTOR CONTROL SYSTEMS; RETROFITTING; TECHNOLOGY TRANSFER
Descriptors DEC
HEAVY WATER MODERATED REACTORS; POWER PLANTS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS

Optional Information

Secondary number(s)
CONF-860610--.