Corrosion damage in the material and the variation of the critical brittleness temperature

1988 ◽  
Vol 24 (3) ◽  
pp. 211-216
Author(s):  
Yu. G. Matvienko
Keyword(s):  
Corrosion Damage ◽  
Critical Brittleness Temperature ◽  
Brittleness Temperature

Conservative estimations of irradiation embrittlement of reactor pressure vessel steels for WWER-1000 lifetime prediction

2019 ◽  
Vol 15 (1) ◽  
pp. 246-257
Author(s):  
Nikolai Petrovich Anosov ◽  
Vladimir Nikolaevich Skorobogatykh ◽  
Lyubov’ Yur’yevna Gordyuk ◽  
Vasilii Anatol’evich Mikheev ◽  
Egor Vasil’yevich Pogorelov ◽  
...  
Keyword(s):  
Transition Temperature ◽  
Brittle Fracture ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Lifetime Prediction ◽  
Critical Brittleness Temperature ◽  
Irradiation Embrittlement ◽  
Content Type ◽  
Brittleness Temperature ◽  
Reactor Pressure

Purpose The purpose of this paper is to consider a procedure of water-water energetic reactor (WWER) reactor pressure vessel (RPV) lifetime prediction at the stages of design and lifetime extension using the standard irradiation embrittlement parameters as defined in regulatory documents. A comparison is made of the brittle fracture resistance (BFR) values evaluated using two criteria: shift in the critical brittleness temperature ΔTc or shift in the brittle-to-ductile transition temperature ΔTp and without shifts (Tc and Tp). Design/methodology/approach The radiation resistance was determined using the following three approaches: calculation based on standard values ΔTc and Tc0 or ΔTp and Tp0 (a level of excessive conservatism); calculation based on standard value ΔTc and actual value Tc0 or actual values ΔTp and Tp0 (the level of realistic conservatism); or calculation based on actual values of Tc and Tc0 or Tp and Tp0 (the level of actual conservatism). The BFR was evaluated based on the results of testing the specimens subjected to irradiation in research reactors as well as surveillance specimens subjected to irradiation immediately under operating conditions. Findings The excessive conservatism in determining the actual lifetime of nuclear reactor vessel materials can be eliminated by using the immediate values of critical brittleness temperature and ductile-to-brittle transition temperature. Originality/value Obtained results can be applied to extend WWER vessel operating time at the stages of designing and operation due to substantiated decrease in conservatism. And it will allow carrying out a statistical substantiated assessment of the resistance to brittle fracture of the RPV steels.

A method of determining the critical brittleness temperature of steel from the energy of crack initiation in the specimen

1990 ◽  
Vol 25 (5) ◽  
pp. 486-488
Author(s):  
Yu. I. Zvezdin ◽  
A. A. Popov ◽  
A. B. Karaev ◽  
B. A. Sugirbekov ◽  
Yu. G. Dragunov
Keyword(s):  
Crack Initiation ◽  
Critical Brittleness Temperature ◽  
Brittleness Temperature

Dose–time dependence of steel critical brittleness temperature for VVER-1000 vessel service life prediction

Atomic Energy ◽  
2011 ◽  
Vol 110 (3) ◽  
pp. 141-150 ◽  
Author(s):  
A. V. Dub ◽  
V. N. Skorobogatykh ◽  
N. P. Anosov ◽  
V. V. Zharov ◽  
A. S. Zubchenko ◽  
...  
Keyword(s):  
Service Life ◽  
Time Dependence ◽  
Life Prediction ◽  
Service Life Prediction ◽  
Critical Brittleness Temperature ◽  
Brittleness Temperature ◽  
Dose Time

Determining the critical brittleness temperature of sheet steel

1979 ◽  
Vol 11 (12) ◽  
pp. 1429-1432
Author(s):  
O. Ya. Znachkovskii ◽  
V. A. Rakovskii ◽  
N. G. Solov'eva
Keyword(s):  
Sheet Steel ◽  
Critical Brittleness Temperature ◽  
Brittleness Temperature

scholarly journals Brittle fracture resistance of reactor pressure vessel steels in the initial state

2018 ◽  
Vol 4 (3) ◽  
pp. 155-161
Author(s):  
Yegor Pogorelov ◽  
Nikolay Anosov ◽  
Vladimir Skorobogatykh ◽  
Lyubov Gordyuk ◽  
Vasiliy Mikheev ◽  
...  
Keyword(s):  
Heat Treatment ◽  
Transition Temperature ◽  
Brittle Fracture ◽  
Fracture Resistance ◽  
Critical Brittleness Temperature ◽  
Initial State ◽  
Brittleness Temperature ◽  
Brittle Fracture Resistance ◽  
The Difference ◽  
Upper Level

The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation). It is proposed to replace the brittle fracture resistance assessment using the critical brittleness temperature TC for the BFR assessment using the brittle-viscous transition temperature TT. Consideration was given to calibration charts used for studying the TT dependence on the grain size and heat treatment. A comparison of the TC and TT values in the experimental industrial 15H2NMFA-A steel billets shows that the TC values are significantly lower than the TT values: – at the lower level of conservatism, the difference between TC and TT is 22 °C; – at the upper level of conservatism, this difference is 24 °C. The array data on the critical brittleness temperature and the ductile-to-brittle transition temperature of impact test samples of 15H2NMFAA (for VVER-1000) and 15H2NMFA grade 1 (for VVER-1200) steels were statistically processed. The industrial shell samples were manufactured at the “Energomashspetsstal” plant (Kramatorsk, Ukraine). It was found that, in the metal of VVER-1000 vessel surveillance specimens with the copper content – less than 0.06%, heat treatment has a significant effect on the TT value, which changes from –99 to –28°C; – from 0.07 to 0.12%, heat treatment has a significant effect on the TT value, which changes from –60 to –40°C.

Effect of chemical and structural nonuniformity of vver vessel steel on the critical brittleness temperature under irradiation

Atomic Energy ◽  
2012 ◽  
Vol 112 (1) ◽  
pp. 38-46 ◽  
Author(s):  
A. V. Doub ◽  
V. N. Skorobogatykh ◽  
N. P. Anosov ◽  
V. V. Zharov ◽  
A. S. Zubchenko ◽  
...  
Keyword(s):  
Critical Brittleness Temperature ◽  
Vessel Steel ◽  
Brittleness Temperature ◽  
Structural Nonuniformity

Determination of the critical brittleness temperature in impact binding

1992 ◽  
Vol 27 (2) ◽  
pp. 165-168
Author(s):  
V. I. Smirnov ◽  
A. Sh. Deich
Keyword(s):  
Critical Brittleness Temperature ◽  
Brittleness Temperature

Segmentation of corrosion damage images with unknown background by energy minimization. Information Extraction and Processing

2018 ◽  
Vol 2018 (46) ◽  
pp. 38-42
Author(s):  
T. S. Mandziy ◽  
◽  
I. B. Ivasenko ◽  
Keyword(s):  
Information Extraction ◽  
Energy Minimization ◽  
Corrosion Damage

Experimental Testing of Older AASHTO Type II Bridge Girders with Corrosion Damage at the Ends

PCI Journal ◽  
2019 ◽  
Vol 64 (1) ◽  
Author(s):  
Cameron D. Murray ◽  
Brittany N. Cranor ◽  
Royce W. Floyd ◽  
Jin-Song Pei
Keyword(s):  
Experimental Testing ◽  
Corrosion Damage ◽  
Bridge Girders ◽  
Type Ii

Development of corrosion flaws for the production of realistic test specimens

2020 ◽  
Vol 64 (1) ◽  
pp. 23-28
Author(s):  
J. Hodač ◽  
Z. Fulín ◽  
P. Mareš ◽  
J. Veselá ◽  
O. Chocholatý
Keyword(s):  
Power Plants ◽  
Galvanic Corrosion ◽  
Water Solution ◽  
Erosive Wear ◽  
Corrosion Damage ◽  
Water Mist ◽  
Carbon Steels ◽  
Bending Stress ◽  
Solution Flow ◽  
Mechanical Bending

AbstractTo produce realistic test specimens with realistic flaws, it is necessary to develop appropriate procedure for corrosion flaw production. Tested specimens are made from steels commonly used in power plants, such as carbon steels, stainless steels and their dissimilar weldments. In this study, corrosion damage from NaCl water solution and NaCl water mist are compared. Specimens were tested with and without mechanical bending stress. The corrosion processes produced plane, pitting and galvanic corrosion. On dissimilar weldments galvanic corrosion was observed and resulted to the deepest corrosion damage. Deepest corrosion flaws were formed on welded samples. The corrosion rate was also affected by the solution flow in a contact with the specimens, which results in a corrosion-erosive wear. Produced flaws are suitable as natural crack initiators or as realistic corrosion flaws in test specimens.

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