PREDICTING THE SERVICE LIFE OF THE HEAT-EXCHANGE BUNDLE OF A STEAM GENERATOR AT A NUCLEAR POWER STATION WITH WATER-MODERATED WATER-COOLED REACTORS WITH RESPECT TO STRESS-CORROSION CONDITIONS.

被引：0

作者：

Sereda, E.V. ^{[1
]}

Gorbatykh, V.P. ^{[1
]}

机构：

[1] Moscow Power Inst MEI, USSR, Moscow Power Inst MEI, USSR

来源：

Thermal Engineering (English translation of Teploenergetika) | 1987年 / 31卷 / 11期

关键词：

NUCLEAR REACTORS; WATER COOLED - Heat Exchangers - STEAM GENERATORS - Heat Exchangers;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Austenitic chrome-nickel stainless steels are used in the nuclear power industry due to their combination of strength and physico-chemical properties. However, when there are certain corrosive components present in the working media these steels have a susceptibility to corrsion under stress. For the case of stress corrosion of austenitic stainless steels in hot chloride solutions a film dislocation approach to describing the mechanism of the process has been proposed by the authors for predicting the kinetics of failure of the heat exchange tubes of steam generators during the course of an operational campaign. Formulas are given for the dependence of rate of development of a corrosion crack on chloride concentration and electrochemical potential. 12Cr18Ni10T: steel was tested.

引用

页码：640 / 641

共 36 条

[31] A MATHEMATICAL-MODEL FOR THE PROCESS OF IN-SERVICE REMOVAL OF DEPOSITS FROM STEAM-GENERATORS OF NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
KOTENKOV, VN
MONAKHOV, AS
DIK, VP
KATKOV, AP
THERMAL ENGINEERING, 1989, 36 (06) : 324 - 327
[32] SELECTION OF PARAMETERS IN DEVELOPING A SEMI-PEAK LOAD GENERATING-UNIT FOR A NUCLEAR-POWER STATION WITH WATER-MODERATED WATER-COOLED REACTORS
RASSOKHIN, NG
ZARANTSYAN, AV
THERMAL ENGINEERING, 1979, 26 (07) : 428 - 430
[33] PROBLEMS OF MATHEMATICAL-MODELING OF THE THERMOHYDRAULIC AND WATER-CHEMISTRY PROCESSES IN THE STEAM-GENERATORS OF NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS
VORONOV, VN
KRASNORYADTSEV, IM
THERMAL ENGINEERING, 1990, 37 (10) : 541 - 545
[34] CALCULATION OF THE QUANTITY OF CORROSION PRODUCT DEPOSITS ON FUEL-ELEMENTS AND OF THEIR RADIONUCLIDES IN THE REACTOR LOOP OF A NUCLEAR-POWER STATION WITH A WATER-MODERATED WATER-COOLED REACTOR
TEVLIN, SA
THERMAL ENGINEERING, 1991, 38 (01) : 12 - 15
[35] THE INFLUENCE OF TEMPERATURE NONUNIFORMITY WITHIN THE VOLUME OF STEAM-GENERATORS OF NUCLEAR-POWER STATIONS WITH WATER-MODERATED WATER-COOLED REACTORS ON THE EFFECTIVENESS OF DOSING CHELATING-AGENTS TO THE FEEDWATER
SHEPELEV, AA
KRASNORYADTSEV, IM
VORONOV, VN
THERMAL ENGINEERING, 1988, 35 (12) : 712 - 714
[36] AUTOMATING THE SUBSYSTEM FOR MONITORING AND CONTROLLING SECONDARY LOOP WATER-CHEMISTRY IN A NUCLEAR-POWER STATION WITH WATER-MODERATED WATER-COOLED REACTORS, BASED ON THE KOMPLEKS TITAN-2 COMPUTER CONTROL COMPLEX
MAMET, VA
NAZARENKO, PN
KISELEV, NG
KOZLOV, VY
FEDOSEEV, MV
TISHCHENKO, ND
THERMAL ENGINEERING, 1991, 38 (12) : 663 - 668

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