Effects of Ti Addition on the Microstructure and Tensile Properties of China Low Activation Martensitic Steel for Nuclear Fusion Reactors

2019 ◽  
Vol 90 (9) ◽  
pp. 1900109 ◽  
Author(s):  
Dongping Zhan ◽  
Guoxing Qiu ◽  
Changsheng Li ◽  
Min Qi ◽  
Zhouhua Jiang ◽  
...  
Keyword(s):  
Tensile Properties ◽  
Martensitic Steel ◽  
Nuclear Fusion ◽  
Fusion Reactors ◽  
Ti Addition

scholarly journals Effects of Y and Ti addition on microstructure stability and tensile properties of reduced activation ferritic/martensitic steel

2019 ◽  
Vol 51 (5) ◽  
pp. 1365-1372 ◽  
Author(s):  
Guoxing Qiu ◽  
Dongping Zhan ◽  
Changsheng Li ◽  
Min Qi ◽  
Zhouhua Jiang ◽  
...  
Keyword(s):  
Tensile Properties ◽  
Martensitic Steel ◽  
Microstructure Stability ◽  
Ti Addition

VALLOUREC VM 125 13Cr SS

Alloy Digest ◽  
2016 ◽  
Vol 65 (11) ◽  
Keyword(s):  
Fracture Toughness ◽  
Corrosion Resistance ◽  
Physical Properties ◽  
Tensile Properties ◽  
Martensitic Steel ◽  
Chloride Content ◽  
Sour Service

Abstract Vallourec VM 125 13Cr SS is a 13Cr super martensitic steel for use in oil country tubular goods as a material suitable for sour service. The CY version offers corrosion and SCC resistance on a greater usage domain than API L80-13Cr in terms of temperature and chloride content. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties as well as fracture toughness. It also includes information on corrosion resistance as well as forming. Filing Code: SS-1254. Producer or source: Vallourec USA Corporation.

Nano-Scale Precipitates of Reduced Activation Steels for the Application of Nuclear Fusion Reactors

2014 ◽  
Vol 34 (3) ◽  
pp. 449-455 ◽  
Author(s):  
S. Moniri ◽  
M. Ghoranneviss ◽  
M. R. Hantehzadeh ◽  
A. Salar Elahi
Keyword(s):  
Nuclear Fusion ◽  
Fusion Reactors ◽  
Nano Scale ◽  
Reduced Activation Steels

scholarly journals Effects of Cr and Mo on Retained Austenite Characteristics and Tensile Properties of TRIP-aided Annealed Martensitic Steel

2012 ◽  
Vol 98 (11) ◽  
pp. 610-617 ◽  
Author(s):  
Junya Kobayashi ◽  
Nobuo Yoshikawa ◽  
Toshio Murakami ◽  
Koh-ichi Sugimoto
Keyword(s):  
Tensile Properties ◽  
Retained Austenite ◽  
Martensitic Steel

W and B4C Coatings for Nuclear Fusion Reactors

1998 ◽  
Author(s):  
A. Cavasin ◽  
T. Brzezinski ◽  
S. Grenier ◽  
M. Smagorinski ◽  
P. Tsantrizos
Keyword(s):  
Inertial Confinement Fusion ◽  
Nuclear Fusion ◽  
Energy Levels ◽  
High Hardness ◽  
Fusion Reactors ◽  
Inertial Confinement ◽  
X Rays ◽  
First Wall ◽  
Term Operation ◽  
Confinement Fusion

Abstract The development of nuclear fusion reactors is presently considered to be the only possible answer to the world's increasing demand for energy, while respecting the environment. Nuclear fusion devices may be broadly divided into two main groups with distinctively different characteristics: magnetic confinement fusion (MCF) and inertial confinement fusion (ICF) reactors. Although the two nuclear fusion technologies show similarities in energy levels (as high as 3 J/cm2) and type of environment (high temperature plasmas) to be contained, the materials of choice for the protective shields (first wall in the ICF and deflectors in the MCF) differ significantly. In ICF reactors, multiple laser beams are used to ignite the fuel in single pulses. This process exposes the first wall to microshrapnel, unconverted light, x-rays, and neutrons. B4C is a low Z material that offers high depth x-ray absorption to minimize surface heating, is not activated by neutrons (will not become radioactive), and offers high hardness and vapour temperature. The long term operation envisioned within MCF reactors, where a continuous nuclear fusion of the fuel is sustained within the confinement of a magnetic field, favours the use of high Z materials, such as W, to protect the plasma exposed deflectors. The reason is a lower erosion rate and a shorter ionization distance in the plasma, which favours the redeposition of the sputtered atoms, both resulting in a lower contamination of the plasma. The production of the first wall and the deflector shields using solid B,C and W materials respectively, is obviously unthinkable. However, ProTeC has developed high density coatings for both ICF and MCF nuclear fusion reactors. W coatings with less then 2% porosity have been produced for both, the Tokamac MCF reactor and its Toroid Fueler. The toroid fueler is a plasma generating device designed to accelerate particles and inject them into the centre of the operating fusion reactor in order to refuel. For the application in an ICF reactor, B4C coatings exhibiting porosity levels below 3% with a hardness above 2500 HV have been deposited directly onto Al substrate. Properties such as outgassing, resistance to erosion and shrapnel, and the influence of x-rays have been studied and showed exceptional results.

scholarly journals Testing of materials perspective for nuclear fusion reactors with inertial plasma confinement by Plasma Focus and laser devices

2019 ◽  
Vol 1347 ◽  
pp. 012071 ◽  
Author(s):  
V A Gribkov ◽  
E V Demina ◽  
E E Kazilin ◽  
S V Latyshev ◽  
S A Maslyaev ◽  
...  
Keyword(s):  
Plasma Focus ◽  
Nuclear Fusion ◽  
Fusion Reactors ◽  
Plasma Confinement ◽  
Laser Devices
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