Substantiation of Recommendations for Ensuring the Design Service Life of Heat-Transfer Tubes Used in a PGV-1000MKP steam generator

被引：0

作者：

Popadchuk V.S. ^{[1
]}

Trunov N.B. ^{[1
]}

Brykov S.I. ^{[1
]}

Zhukov R.Yu. ^{[1
]}

Tupikov R.A. ^{[1
]}

Seleznev A.V. ^{[1
]}

Popkov R.I. ^{[1
]}

Metal'nikov M.S. ^{[1
]}

Styazhkin P.S. ^{[2
]}

Karzov G.P. ^{[3
]}

Suvorov S.A. ^{[3
]}

机构：

[1] OAO Gidropress Experimental Design Office, Podolsk, Moscow Oblast, 142103

[2] OAO Head Institute VNIPIET, St. Petersburg, 197183

[3] Prometei Central Research Institute of Structural Materials, Federal State Unitary Enterprise, St. Petersburg, 191115

来源：

Thermal Engineering | 2011年 / 58卷 / 3期

关键词：

Steam Generator; Nuclear Power Station; Tube Bundle; Coolant Circuit; Shutdown Mode;

D O I：

10.1134/S0040601511030104

中图分类号：

学科分类号：

摘要：

We present the results obtained from tests and studies carried out on the model of tube bundles for a PGV-1000 horizontal steam generator that were conducted for experimentally substantiating the design service life of a steam generator tube bundle intended for use at new nuclear power stations equipped with a PGV-1000MKP steam generator. Measures taken to minimize the incipience and development of local corrosion damage to the heat-transfer tubes and ensure their design service life are substantiated and confirmed. © Pleiades Publishing Inc. 2011.

引用

页码：190 / 201

页数：11

共 9 条

[1] Optimizing the Design of the Steam-Receiving Perforated Sheet Used in the PGV-1000MKO Steam Generator
Volkova, V. Yu.
Golibrodo, L. A.
Krutikov, A. A.
Kudryavtsev, O. V.
Skibin, A. P.
Sotskov, V. V.
THERMAL ENGINEERING, 2020, 67 (08) : 524 - 535
[2] Optimizing the Design of the Steam-Receiving Perforated Sheet Used in the PGV-1000MKO Steam Generator
V. Yu. Volkov
L. A. Golibrodo
A. A. Krutikov
O. V. Kudryavtsev
A. P. Skibin
V. V. Sotskov
Thermal Engineering, 2020, 67 : 524 - 535
[3] Specific features of corrosion damage to heat-transfer tubes of steam generators used at nuclear power stations equipped with VVER-1000 reactors
Nemytov D.S.
Tyapkov V.F.
Thermal Engineering, 2009, 56 (7) : 612 - 616
[4] Modeling of Thermohydraulic Processes in a Steam Generator with Several Plugged Heat-Transfer Tubes
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L. A. Goliborodo
A. A. Krutikov
O. V. Kudryavtsev
Thermal Engineering, 2022, 69 : 77 - 86
[5] Modeling of Thermohydraulic Processes in a Steam Generator with Several Plugged Heat-Transfer Tubes
Volkov, V. Yu
Goliborodo, L. A.
Krutikov, A. A.
Kudryavtsev, O., V
THERMAL ENGINEERING, 2022, 69 (02) : 77 - 86
[6] Structure Analysis on Tube-Sheets and Heat-Transfer Tubes of PWR Steam Generator
Xu, Junfeng
Ye, Jianping
ADVANCED BUILDING MATERIALS AND STRUCTURAL ENGINEERING, 2012, 461 : 421 - +
[7] Life calculations for header - PGV-1000 steam generator connector weld joints under NPP service conditions
Stepanov G.V.
Kharchenko V.V.
Babutskii A.I.
Romanov S.V.
Feofentov N.A.
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Strength of Materials, 2004, 36 (3) : 321 - 326
[8] Simulating the rolling of tubes and its effect on the stressed and strain state of the tube sheets used in the heat-transfer apparatuses of steam turbine units
M. F. Tselishchev
P. N. Plotnikov
Thermal Engineering, 2008, 55 (3) : 219 - 222
[9] An analysis of factors causing the occurrence of off-design thermally induced force effects in the zone of weld joint no. 111-1 in a PGV-1000m steam generator and recommendations on excluding them
Bakirov M.B.
Levchuk V.I.
Povarov V.P.
Gromov A.F.
Thermal Engineering, 2014, 61 (08) : 541 - 550

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