Estimation of Uniaxial Material Properties by Small Punch Testing to Support Post-Irradiation Examination of Reactor Pressure Vessel Steels

2021 ◽  
Author(s):  
Stefan Holmstrom ◽  
Oliver Martin ◽  
Theo Bakker ◽  
Murthy Kolluri ◽  
Matthias Bruchhausen
Keyword(s):  
Pressure Vessel ◽  
Material Properties ◽  
Reactor Pressure Vessel ◽  
Small Punch ◽  
Post Irradiation ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

Influence of the Irradiation Temperature on the Formation of Defects in Reactor Pressure Vessel Steels

1996 ◽  
Vol 439 ◽  
Author(s):  
M. Große ◽  
A. Hempel ◽  
J. Böhmert ◽  
G. Brauer ◽  
F. M. Haggag
Keyword(s):  
Pressure Vessel ◽  
Irradiation Temperature ◽  
Reactor Pressure Vessel ◽  
Pressure Vessel Steel ◽  
Vessel Steel ◽  
Post Irradiation ◽  
Cu Content ◽  
Reactor Pressure Vessel Steel ◽  
Pressure Vessel Steels ◽  
Reactor Pressure

AbstractTwo heats of reactor pressure vessel steel type A533-B-1 differing in their Cu content (0.07 and 0.14 wt.-%) were irradiated to a fluence of 1* 1018 neutrons/cm2 at temperatures of 60, 121, and 288 °C, respectively. Their microstructure has been studied by SANS, SAXS, and PAS in the asirradiated and post-irradiation annealed stages and compared to the behaviour of unirradiated material and the results are discussed.

Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt

2016 ◽  
Author(s):  
Yongjian Gao ◽  
Yinbiao He ◽  
Ming Cao ◽  
Yuebing Li ◽  
Shiyi Bao ◽  
...  
Keyword(s):  
Pressure Vessel ◽  
Material Properties ◽  
Power Plants ◽  
Structural Integrity ◽  
Plastic Material ◽  
Plastic Region ◽  
Reactor Pressure Vessel ◽  
Elastic Plastic ◽  
Elastic Plastic Material ◽  
Reactor Pressure

In-Vessel Retention (IVR) is one of the most important severe accident mitigation strategies of the third generation passive Nuclear Power Plants (NPP). It is intended to demonstrate that in the case of a core melt, the structural integrity of the Reactor Pressure Vessel (RPV) is assured such that there is no leakage of radioactive debris from the RPV. This paper studied the IVR issue using Finite Element Analyses (FEA). Firstly, the tension and creep testing for the SA-508 Gr.3 Cl.1 material in the temperature range of 25°C to 1000°C were performed. Secondly, a FEA model of the RPV lower head was built. Based on the assumption of ideally elastic-plastic material properties derived from the tension testing data, limit analyses were performed under both the thermal and the thermal plus pressure loading conditions where the load bearing capacity was investigated by tracking the propagation of plastic region as a function of pressure increment. Finally, the ideal elastic-plastic material properties incorporating the creep effect are developed from the 100hr isochronous stress-strain curves, limit analyses are carried out as the second step above. The allowable pressures at 0 hr and 100 hr are obtained. This research provides an alternative approach for the structural integrity evaluation for RPV under IVR condition.

Manufacturing and Properties of Closure Head Forging Integrated With Flange for PWR Reactor Pressure Vessel

2004 ◽  
Author(s):  
Komei Suzuki ◽  
Etsuo Murai ◽  
Yasuhiko Tanaka ◽  
Iku Kurihara ◽  
Tomoharu Sasaki ◽  
...  
Keyword(s):  
Weld Joint ◽  
Pressure Vessel ◽  
Material Properties ◽  
Impact Test ◽  
Structural Integrity ◽  
Reactor Pressure Vessel ◽  
Conventional Design ◽  
Manufacturing Technologies ◽  
Reactor Pressure

Closure head forging (SA508, Gr.3 Cl.1) integrated with flange for PWR reactor pressure vessel has been developed. This is intended to enhance structural integrity of closure head resulted in elimination of ISI, by eliminating weld joint between closure head and flange in the conventional design. Manufacturing procedures have been established so that homogeneity and isotropy of the material properties can be assured in the closure head forging integrated with flange. Acceptance tensile and impact test specimens are taken and tested regarding the closure head forging integrated with flange as very thick and complex forgings. This paper describes the manufacturing technologies and material properties of the closure head forging integrated with flange.

Thermodynamic models of low-temperature Mn–Ni–Si precipitation in reactor pressure vessel steels

2014 ◽  
Vol 4 (3) ◽  
pp. 101-105 ◽  
Author(s):  
Wei Xiong ◽  
Huibin Ke ◽  
Ramanathan Krishnamurthy ◽  
Peter Wells ◽  
Leland Barnard ◽  
...  
Keyword(s):  
Low Temperature ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Thermodynamic Models ◽  
Pressure Vessel Steels ◽  
Image Position ◽  
Reactor Pressure

Abstract

scholarly journals 3-D Atom Probe Observation of Solute Atom Clusters in Reactor Pressure Vessel Steels

Materia Japan ◽  
2008 ◽  
Vol 47 (12) ◽  
pp. 619-619
Author(s):  
Kenji Nishida ◽  
Kenji Dohi ◽  
Akiyoshi Nomoto ◽  
Naoki Soneda
Keyword(s):  
Pressure Vessel ◽  
Solute Atom ◽  
Atom Probe ◽  
Reactor Pressure Vessel ◽  
Atom Clusters ◽  
Pressure Vessel Steels ◽  
Reactor Pressure
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