scholarly journals The Elevated Temperature and Thermal Shock Fracture Toughnesses of Nuclear Pressure Vessel Steel

1979 ◽  
Vol 28 (308) ◽  
pp. 421-426
Author(s):  
Kazumi HIRANO ◽  
Hideo KOBAYASHI ◽  
Hajime NAKAZAWA ◽  
Atsushi NARA
Keyword(s):  
Elevated Temperature ◽  
Thermal Shock ◽  
Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel

Measurements of Stress During Thermal Shock in Clad Reactor Pressure Vessel Material Using Time-Resolved In-Situ Synchrotron X-Ray Diffraction

2018 ◽  
Author(s):  
Sam Oliver ◽  
Chris Simpson ◽  
Andrew James ◽  
Christina Reinhard ◽  
David Collins ◽  
...  
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Pressure Vessels ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steel ◽  
X Ray Diffraction ◽  
Time Resolved ◽  
Vessel Steel ◽  
X Ray ◽  
Reactor Pressure

Nuclear reactor pressure vessels must be able to withstand thermal shock due to emergency cooling during a loss of coolant accident. Demonstrating structural integrity during thermal shock is difficult due to the complex interaction between thermal stress, residual stress, and stress caused by internal pressure. Finite element and analytic approaches exist to calculate the combined stress, but validation is limited. This study describes an experiment which aims to measure stress in a slice of clad reactor pressure vessel during thermal shock using time-resolved synchrotron X-ray diffraction. A test rig was designed to subject specimens to thermal shock, whilst simultaneously enabling synchrotron X-ray diffraction measurements of strain. The specimens were extracted from a block of SA508 Grade 4N reactor pressure vessel steel clad with Alloy 82 nickel-base alloy. Surface cracks were machined in the cladding. Electric heaters heat the specimens to 350°C and then the surface of the cladding is quenched in a bath of cold water, representing thermal shock. Six specimens were subjected to thermal shock on beamline I12 at Diamond Light Source, the UK’s national synchrotron X-ray facility. Time-resolved strain was measured during thermal shock at a single point close to the crack tip at a sample rate of 30 Hz. Hence, stress intensity factor vs time was calculated assuming K-controlled near-tip stress fields. This work describes the experimental method and presents some key results from a preliminary analysis of the data.

scholarly journals In-situ measurements of stress during thermal shock in clad pressure vessel steel using synchrotron X-ray diffraction

2021 ◽  
Vol 192 ◽  
pp. 106136
Author(s):  
Sam Oliver ◽  
Chris Simpson ◽  
David M. Collins ◽  
Christina Reinhard ◽  
Martyn Pavier ◽  
...  
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
In Situ Measurements ◽  
Pressure Vessel Steel ◽  
X Ray Diffraction ◽  
Vessel Steel ◽  
X Ray

Cleavage and Ductile Thermal Shock Fractures of Corner-Cracked Nozzles

1989 ◽  
Vol 111 (3) ◽  
pp. 241-246 ◽  
Author(s):  
G. Yagawa ◽  
K. Ishihara
Keyword(s):  
Thermal Shock ◽  
Pressure Vessel ◽  
Structural Integrity ◽  
Three Dimensional ◽  
Pressure Vessel Steel ◽  
Fracture Parameter ◽  
The Finite Element Method ◽  
Vessel Steel ◽  
Pressurized Thermal Shock ◽  
Reactor Pressure

In order to study the structural integrity of the reactor pressure vessel under pressurized thermal shock, both the cleavage and the ductile thermal shock fracture experiments using initially corner-cracked nozzle specimens made of Type A508 class 3 pressure vessel steel were performed. In both experiments, unstable fractures were realized, although the test conditions were very conservative compared to those of real plants. Finally, the three-dimensional and time-dependent fracture parameter obtained with the finite element method was successfully employed to discuss the fracture phenomenon.

Elevated-Temperature Mechanical Behavior of a Carbon-Manganese Pressure Vessel Steel

1977 ◽  
Vol 99 (4) ◽  
pp. 359-365
Author(s):  
J. G. Early
Keyword(s):  
Elevated Temperature ◽  
Fracture Mode ◽  
Pressure Vessel ◽  
Material Constant ◽  
Creep Rupture ◽  
Pressure Vessel Steel ◽  
Aging Effects ◽  
Stress Regime ◽  
Vessel Steel ◽  
Short Time

The short-time effects of stress and temperature on the mechanical properties of a carbon-manganese pressure vessel steel were investigated using room- and elevated-temperature tensile tests and short-time creep-rupture tests. The tensile test results indicated that strain aging effects were not Significant in the temperature range 593 to 677 C (1100 to 1250 F). Analysis of the creep-rupture data, in the range 621 to 677 (1150 to 1250 F), by the Larson-Miller method using the procedure of Manson and Mendelson yielded a value of 20.7 for the material constant, C. In the temperature and stress regime studied, a linear relationship was observed between log (stress) and log (time-to-rupture). Fractographic analyses revealed a common fracture mode in all specimens tested. The fracture mode is described as an intermediate type, containing features of both transgranular and intergranular fracture.

Dislocation structures in 16MND5 pressure vessel steel strained in uniaxial tension at −196°C

2005 ◽  
Vol 96 (8) ◽  
pp. 909-912
Author(s):  
Karel Obrtlík ◽  
Christian Robertson ◽  
Bernard Marini
Keyword(s):  
Uniaxial Tension ◽  
Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel

scholarly journals Micromagnetic Characterization of Operation-Induced Damage in Charpy Specimens of RPV Steels

2021 ◽  
Vol 11 (7) ◽  
pp. 2917
Author(s):  
Madalina Rabung ◽  
Melanie Kopp ◽  
Antal Gasparics ◽  
Gábor Vértesy ◽  
Ildikó Szenthe ◽  
...  
Keyword(s):  
Neutron Irradiation ◽  
Pressure Vessel ◽  
Operating Conditions ◽  
Magnetic Characteristics ◽  
Pressure Vessel Steel ◽  
Training Procedure ◽  
Vessel Steel ◽  
Before And After ◽  
The Individual ◽  
Magnetic Adaptive Testing

The embrittlement of two types of nuclear pressure vessel steel, 15Kh2NMFA and A508 Cl.2, was studied using two different methods of magnetic nondestructive testing: micromagnetic multiparameter microstructure and stress analysis (3MA-X8) and magnetic adaptive testing (MAT). The microstructure and mechanical properties of reactor pressure vessel (RPV) materials are modified due to neutron irradiation; this material degradation can be characterized using magnetic methods. For the first time, the progressive change in material properties due to neutron irradiation was investigated on the same specimens, before and after neutron irradiation. A correlation was found between magnetic characteristics and neutron-irradiation-induced damage, regardless of the type of material or the applied measurement technique. The results of the individual micromagnetic measurements proved their suitability for characterizing the degradation of RPV steel caused by simulated operating conditions. A calibration/training procedure was applied on the merged outcome of both testing methods, producing excellent results in predicting transition temperature, yield strength, and mechanical hardness for both materials.

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