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Results of studies of the thermohydraulics of the primary pumps in PWR reactors

Abstract

In the context of its nuclear-safety program for pressurized-water reactors, E.D.F. has engaged in theoretical and experimental studies in order to gain better knowledge of the behaviour of a pump under accident conditions, with passage to diphasic regime. The results of these studies are presented here, both from the experimental and theoretical points of view. They show in particular that the behaviour of the pump is essentially dictated by the interfacial friction for small flows, and by the appearance of a critical flow rate for large flows. The outline of the theoretical model describing the operation of the pump in the first three quadrants (positive and negative flow, positive and negative rotation) is described, as are certain special applications of the model, such as the determination of racing velocities in diphasic conditions.
Authors:
Grison, P; Laura, J F [1] 
  1. E.D.F., Chatou (France)
Publication Date:
Jan 01, 1982
Product Type:
Journal Article
Reference Number:
FR-83-03092; EDB-84-009848
Resource Relation:
Journal Name: Houille Blanche; (France); Journal Volume: 7-8
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PUMPS; FLOW RATE; HYDRAULICS; PWR TYPE REACTORS; CRITICAL FLOW; INTERNAL FRICTION; LOSS OF COOLANT; MATHEMATICAL MODELS; OPERATION; PRESSURE MEASUREMENT; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; TEST FACILITIES; TESTING; TWO-PHASE FLOW; VOID FRACTION; ACCIDENTS; COOLING SYSTEMS; ENERGY SYSTEMS; FLUID FLOW; FLUID MECHANICS; FRICTION; MECHANICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
5455687
Country of Origin:
France
Language:
French
Other Identifying Numbers:
Journal ID: CODEN: HOBLA
Submitting Site:
HEDB
Size:
Pages: 655-663
Announcement Date:

Citation Formats

Grison, P, and Laura, J F. Results of studies of the thermohydraulics of the primary pumps in PWR reactors. France: N. p., 1982. Web. doi:10.1051/lhb/1982052.
Grison, P, & Laura, J F. Results of studies of the thermohydraulics of the primary pumps in PWR reactors. France. doi:10.1051/lhb/1982052.
Grison, P, and Laura, J F. 1982. "Results of studies of the thermohydraulics of the primary pumps in PWR reactors." France. doi:10.1051/lhb/1982052. https://www.osti.gov/servlets/purl/10.1051/lhb/1982052.
@misc{etde_5455687,
title = {Results of studies of the thermohydraulics of the primary pumps in PWR reactors}
author = {Grison, P, and Laura, J F}
abstractNote = {In the context of its nuclear-safety program for pressurized-water reactors, E.D.F. has engaged in theoretical and experimental studies in order to gain better knowledge of the behaviour of a pump under accident conditions, with passage to diphasic regime. The results of these studies are presented here, both from the experimental and theoretical points of view. They show in particular that the behaviour of the pump is essentially dictated by the interfacial friction for small flows, and by the appearance of a critical flow rate for large flows. The outline of the theoretical model describing the operation of the pump in the first three quadrants (positive and negative flow, positive and negative rotation) is described, as are certain special applications of the model, such as the determination of racing velocities in diphasic conditions.}
doi = {10.1051/lhb/1982052}
journal = {Houille Blanche; (France)}
volume = {7-8}
journal type = {AC}
place = {France}
year = {1982}
month = {Jan}
}