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 16 条

[1] Predicting the build-up of deposits of corrosion products on the heat-transfer surfaces of a PGV-1000M steam generator
Kharitonov, Yu.V.
Brykov, S.I.
Trunov, N.B.
Teploenergetika, 2001, (08): : 20 - 22
[2] 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
[3] 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
[4] 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
[5] Modeling of Thermohydraulic Processes in a Steam Generator with Several Plugged Heat-Transfer Tubes
V. Yu. Volkov
L. A. Goliborodo
A. A. Krutikov
O. V. Kudryavtsev
Thermal Engineering, 2022, 69 : 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 - +
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Stepanov G.V.
Kharchenko V.V.
Babutskii A.I.
Romanov S.V.
Feofentov N.A.
Kravchenko I.V.
Strength of Materials, 2004, 36 (3) : 321 - 326
[8] POST-DRYOUT HEAT-TRANSFER IN STEAM-GENERATOR TUBES AT HIGH-PRESSURES
UNAL, HC
VANGASSELT, MLG
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1983, 26 (03) : 459 - 464
[9] NUMERICAL SIMULATION OF FRETTING WEAR OF HEAT-TRANSFER TUBES IN STEAM GENERATOR UNDER RANDOM EXCITATION FORCES
Tang, Lichen
Qian, Hao
Xie, Yongcheng
Jing, Yi
Huo, Yongzhong
PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 1, 2016,
[10] 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

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