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PMK-2. Experimental study on steam generator behaviour

Abstract

The PMK-2 is a full pressure scaled-down model of the Paks Nuclear Power Plant, with a 1:2070 scaling ratio for the volume and power. It has a steam generator model which is a vertical section of the horizontal steam generator. The model has hot and cold collectors similarly to the steam generators of the plant. The heat transfer tubes are horizontal tubes. There are 82 rows of tubes and the elevations, as well as the heat transfer surface distribution is the same as in the plant. The elevation of the feed water supply is similar to that of the plant. To study the temperature distribution in both the primary and the secondary side several thermocouples are built in, in addition to the overall instrumentation of the loop which has again a high number of measurement channels. Paper gives a description and results of SPE-4, with special respect to the steam generator behaviour in both steady state and transient conditions. Axial distribution of coolant and feedwater temperatures are given for the primary and the secondary side of hot and cold collectors and the temperature distribution in the centre of steam generator. (orig.).
Authors:
Ezsoel, G; Szabados, L; Trosztel, I [1] 
  1. KFKI Atomic Energy Research Inst., Budabest (Hungary)
Publication Date:
Dec 31, 1995
Product Type:
Conference
Report Number:
LTKK-TJ-43; CONF-9410509-
Reference Number:
SCA: 210200; PA: AIX-29:032353; EDB-98:066373; SN: 98001970760
Resource Relation:
Conference: 3. international seminar on horizontal steam generators, Lappeenranta (Finland), 18-20 Oct 1994; Other Information: DN: 1 ref.; PBD: 1995; Related Information: Is Part Of Third international seminar on horizontal steam generators; PB: 430 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FEEDWATER; HEAT TRANSFER; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY EXPERIMENTS; SCALE MODELS; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; TRANSIENTS; WWER TYPE REACTORS
OSTI ID:
614731
Research Organizations:
Lappeenranta Univ. of Technology (Finland).
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE98626444; ISBN 951-763-942-2; TRN: FI9800069032353
Availability:
INIS; OSTI as DE98626444
Submitting Site:
FIN
Size:
pp. 10-32
Announcement Date:
Jun 26, 1998

Citation Formats

Ezsoel, G, Szabados, L, and Trosztel, I. PMK-2. Experimental study on steam generator behaviour. Finland: N. p., 1995. Web.
Ezsoel, G, Szabados, L, & Trosztel, I. PMK-2. Experimental study on steam generator behaviour. Finland.
Ezsoel, G, Szabados, L, and Trosztel, I. 1995. "PMK-2. Experimental study on steam generator behaviour." Finland.
@misc{etde_614731,
title = {PMK-2. Experimental study on steam generator behaviour}
author = {Ezsoel, G, Szabados, L, and Trosztel, I}
abstractNote = {The PMK-2 is a full pressure scaled-down model of the Paks Nuclear Power Plant, with a 1:2070 scaling ratio for the volume and power. It has a steam generator model which is a vertical section of the horizontal steam generator. The model has hot and cold collectors similarly to the steam generators of the plant. The heat transfer tubes are horizontal tubes. There are 82 rows of tubes and the elevations, as well as the heat transfer surface distribution is the same as in the plant. The elevation of the feed water supply is similar to that of the plant. To study the temperature distribution in both the primary and the secondary side several thermocouples are built in, in addition to the overall instrumentation of the loop which has again a high number of measurement channels. Paper gives a description and results of SPE-4, with special respect to the steam generator behaviour in both steady state and transient conditions. Axial distribution of coolant and feedwater temperatures are given for the primary and the secondary side of hot and cold collectors and the temperature distribution in the centre of steam generator. (orig.).}
place = {Finland}
year = {1995}
month = {Dec}
}