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Experience in vibro-acoustic control of primary coolant circuit aggregates

Journal Article:

Abstract

Fundamental principles and possibilities of vibro-acoustic control of the primary coolant circuit in nuclear power plants for detecting failures (slack parts, penetration of foreign bodies, crack formation, etc.) are presented. As a result of pressure and flow rate fluctuations such failures give rise to characteristic changes in apmplitude and frequency of vibration and technological noise from the different aggregates with respect to a 'calibration' spectrum taken in the intact state. Nature and location of the failures may be determined by statistical analysis of the signals recorded from pressure and acceleration gauges. Certain parts of the primary circuit are controlled, especially the main circulation pumps. Additionally, neutron noise has been measured in order to control the core insertions. The method is illustrated by means of measurements performed in the units 1 to 4 of the Novovoronezh nuclear power plant during start-up operation and continuous operation.
Authors:
Sedov, V K; Adamenkov, K A [1] 
  1. Nuclear power plant Novo-Voronesh (USSR)
Publication Date:
Oct 01, 1977
Product Type:
Journal Article
Reference Number:
AIX-08-338225; ERA-03-000641; EDB-77-145095
Resource Relation:
Journal Name: Kernenergie; (German Democratic Republic); Journal Volume: 20:10; Other Information: Translation of 'Desyatiletnij opyt ehksplutatsii Novovoroneshskoj AEhS', Novo-Voronesh 1974, p. 116-125
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PRIMARY COOLANT CIRCUITS; ACOUSTIC MONITORING; WWER TYPE REACTORS; WWER-1 REACTOR; WWER-2 REACTOR; WWER-3 REACTOR; WWER-4 REACTOR; FAILURES; FLUCTUATIONS; MECHANICAL VIBRATIONS; NOISE; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; MONITORING; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
7215512
Country of Origin:
Germany
Language:
German
Other Identifying Numbers:
Journal ID: CODEN: KERNA
Submitting Site:
INIS
Size:
Pages: 328-331
Announcement Date:
Oct 01, 1977

Journal Article:

Citation Formats

Sedov, V K, and Adamenkov, K A. Experience in vibro-acoustic control of primary coolant circuit aggregates. Germany: N. p., 1977. Web.
Sedov, V K, & Adamenkov, K A. Experience in vibro-acoustic control of primary coolant circuit aggregates. Germany.
Sedov, V K, and Adamenkov, K A. 1977. "Experience in vibro-acoustic control of primary coolant circuit aggregates." Germany.
@misc{etde_7215512,
title = {Experience in vibro-acoustic control of primary coolant circuit aggregates}
author = {Sedov, V K, and Adamenkov, K A}
abstractNote = {Fundamental principles and possibilities of vibro-acoustic control of the primary coolant circuit in nuclear power plants for detecting failures (slack parts, penetration of foreign bodies, crack formation, etc.) are presented. As a result of pressure and flow rate fluctuations such failures give rise to characteristic changes in apmplitude and frequency of vibration and technological noise from the different aggregates with respect to a 'calibration' spectrum taken in the intact state. Nature and location of the failures may be determined by statistical analysis of the signals recorded from pressure and acceleration gauges. Certain parts of the primary circuit are controlled, especially the main circulation pumps. Additionally, neutron noise has been measured in order to control the core insertions. The method is illustrated by means of measurements performed in the units 1 to 4 of the Novovoronezh nuclear power plant during start-up operation and continuous operation.}
journal = {Kernenergie; (German Democratic Republic)}
volume = {20:10}
journal type = {AC}
place = {Germany}
year = {1977}
month = {Oct}
}