Published 1999 | Version v1
Book Metadata-only

Dynamic response of the SDS flow-measurement system in CANDU

Creators

  • 1. Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)
  • 2. Ontario Power Generation, Toronto, Ontario (Canada)

Description

Safety analyses of design basis accidents place upper limits on the dynamic response of safety related flow-measurement equipment in CANDU. This study was initiated by the Loss-Of-Flow (LOF) trip-coverage improvement project at Darlington Nuclear Generating Division (DNGD), Ontario Hydro, where, in the fall of 1997 a program was instituted to measure, readjust and validate the response time of the primary heat transport (PHT) safety system flow transmitters across all 4 units with non-intrusive, in-situ, flow-noise measurements. This report summarizes the methods developed for flow-noise analysis and describes results of tests to ensure the validity of underlying assumptions in this type of analysis. (author)

Availability note (English)

Available on CD-ROM from Canadian Nuclear Association, Toronto, Ontario, Canada M5J 2L7
Part of:
Proceedings of the 39. annual Canadian Nuclear Association conference and 20. annual Canadian Nuclear Society conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Association, Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
Imprint Title
Proceedings of the 39. annual Canadian Nuclear Association conference and 20. annual Canadian Nuclear Society conference
Imprint Pagination
640 Megabytes
Journal Page Range
(Session B1) [12 p.]
ISSN
0227-1907

Conference

Title
Communicating the nuclear advantage
Dates
30 May - 2 Jun 1999
Place
Montreal, PQ (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
32002717
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CANDU TYPE REACTORS; DYNAMICS; FLOW REGULATORS; HEAT TRANSFER; PRIMARY COOLANT CIRCUITS; REACTOR CONTROL SYSTEMS; REACTOR SHUTDOWN; RESPONSE FUNCTIONS; SAFETY ANALYSIS
Descriptors DEC
CONTROL EQUIPMENT; CONTROL SYSTEMS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; FUNCTIONS; HEAVY WATER MODERATED REACTORS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SHUTDOWN; THERMAL REACTORS

Optional Information

Notes
4 refs., 3 tabs., 6 figs.