Effect of Hydrogen on the Fracture Toughness of the Titanium Alloys Ti6Al4V and Ti5Al2.5Sn Before and after Neutron Irradiation

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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Fracture Toughness of Powder Metallurgy and Ingot Titanium Alloys – A Review

Key Engineering Materials ◽

10.4028/www.scientific.net/kem.551.143 ◽

2013 ◽

Vol 551 ◽

pp. 143-160 ◽

Cited By ~ 1

Author(s):

Ajit Pal Singh ◽

Brian Gabbitas ◽

De Liang Zhang

Keyword(s):

Fracture Toughness ◽

Powder Metallurgy ◽

Titanium Alloys ◽

Alloy Composition ◽

Low Cost ◽

Ingot Metallurgy ◽

Metal Powders ◽

Critical Factors ◽

Microstructural Characteristics ◽

High Degree

Powder metallurgy (PM) is potentially capable of producing homogeneous titanium alloys at relative low cost compared to ingot metallurgy (IM). There are many established PM methods for consolidating metal powders to near net shapes with a high degree of freedom in alloy composition and resulting microstructural characteristics. The mechanical properties of titanium and its alloys processed using a powder metallurgical route have been studied in great detail; one major concern is that ductility and toughness of materials produced by a PM route are often lower than those of corresponding IM materials. The aim of this paper is to review the fracture toughness of both PM and IM titanium alloys. The effects of critical factors such as interstitial impurities, microstructural features and heat treatment on fracture toughness are also discussed

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Neutron irradiation effects on thermal shock resistance and fracture toughness of graphites as plasma-facing first wall components for fusion reactor devices

Carbon ◽

10.1016/0008-6223(89)90001-8 ◽

1989 ◽

Vol 27 (4) ◽

pp. 507-516 ◽

Cited By ~ 8

Author(s):

S. Sato ◽

A. Kurumada ◽

K. Kawamata ◽

T. Takizawa ◽

K. Teruyama

Keyword(s):

Fracture Toughness ◽

Thermal Shock ◽

Neutron Irradiation ◽

Thermal Shock Resistance ◽

Fusion Reactor ◽

First Wall ◽

Irradiation Effects ◽

Shock Resistance ◽

Wall Components

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06/01174 Evaluation of ductile-brittle transition temperature before and after neutron irradiation for RPV steels using small punch tests

Fuel and Energy Abstracts ◽

10.1016/s0140-6701(06)81178-1 ◽

2006 ◽

Vol 47 (3) ◽

pp. 177

Keyword(s):

Transition Temperature ◽

Neutron Irradiation ◽

Small Punch ◽

Brittle Transition ◽

Ductile Brittle Transition Temperature ◽

Before And After ◽

Brittle Transition Temperature

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The neutron irradiation effects on the temperature dependencies of the electrical conductivity of nanosilicon particles

Modern Physics Letters B ◽

10.1142/s0217984917502578 ◽

2017 ◽

Vol 31 (28) ◽

pp. 1750257 ◽

Cited By ~ 1

Author(s):

Elchin Huseynov ◽

Aydan Garibli

Keyword(s):

Electrical Conductivity ◽

Neutron Flux ◽

Neutron Irradiation ◽

Silicon Nanoparticles ◽

Activation Energies ◽

Radiation Defects ◽

Irradiation Effects ◽

Active Radiation ◽

Before And After ◽

Effects Of Temperature

The effects of temperature and neutron irradiation on the silicon nanoparticles have been studied at different frequencies. It has been defined that additional electro-active radiation defects occur in the silicon nanomaterial after neutron irradiation. Therefore, the change of neutron flux at the interval of [Formula: see text]–[Formula: see text] increases the conductivity of nanosilicon. Activation energies of the silicon nanoparticles were calculated for 10 different constant frequencies according to Arrhenius approach before and after neutron irradiation. The mechanism of electrical conductivity which explains results has been established.

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Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Before and After Irradiation

Volume 1A: Codes and Standards ◽

10.1115/pvp2018-84804 ◽

2018 ◽

Author(s):

Mikhail A. Sokolov

Keyword(s):

Fracture Toughness ◽

Pressure Vessel ◽

Master Curve ◽

Collaborative Program ◽

Before And After ◽

Minimum Number ◽

Real Practice ◽

Reactor Pressure ◽

Good Agreement

Mini-CT specimens are becoming a highly popular geometry for use in reactor pressure vessel (RPV) community for direct measurement of fracture toughness in the transition region using the Master Curve methodology. In the present study, Mini-CT specimens were machined from previously tested Charpy specimens of the Midland low upper-shelf Linde 80 weld in both, unirradiated and irradiated conditions. The irradiated specimens have been characterized as part of a joint ORNL-EPRI-CRIEPI collaborative program. The Linde 80 weld was selected because it has been extensively characterized in the irradiated condition by conventional specimens, and because of the need to validate application of Mini-CT specimens for low upper-shelf materials — a more likely case for some irradiated materials of older generation RPVs. It is shown that the fracture toughness reference temperatures, To, derived from these Mini-CT specimens are in good agreement with To values previously recorded for this material in the unirradiated and irradiated conditions. However, this study indicates that in real practice it is highly advisable to use a much larger number of specimens than the minimum number prescribed in ASTM E1921.

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