Published February 1991 | Version v1
Report Metadata-only

Experimental investigations of ex-core power control system parameters at nuclear power plants with WWER-1000 type reactors

Creators

  • 1. R and D Inst. of Instrumentation Engineering (USSR)

Description

The ex-core instrumentation system (ECIS) mock-up for monitoring the energy distribution over the core volume is described. The experimental investigation of the ECIS mock-up at the running NPP with the use of a representative amount of the reactor conditions has shown the high accuracy and quick response of the ex-core control method of the power and its distribution in the core volume. The small amount of the detectors, the application of the fast algorithms for signal processing make it possible to control the power distribution in the real time. The algorithms for processing detector readings and the results of the tests are also produced. (author). 5 figs

Part of:
Safety implications of computerized process control in nuclear power plants

Additional details

Publishing Information

Imprint Title
Safety implications of computerized process control in nuclear power plants
Imprint Pagination
192 p.
Journal Page Range
p. 163-177.
Report number
IAEA-TECDOC--581

Conference

Title
Technical committee meeting on safety implications of computerized process control in nuclear power plants.
Dates
13-17 Nov 1989.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22038177
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; CALIBRATION; MOCKUP; PERFORMANCE TESTING; POWER DISTRIBUTION; REACTOR CORES; REACTOR MONITORING SYSTEMS; WWER TYPE REACTORS
Descriptors DEC
DISTRIBUTION; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information