Corrosion Problems in Nuclear Fusion Reactors

2020 ◽  
pp. 35-46
Author(s):  
V. Coen
Keyword(s):  
Nuclear Fusion ◽  
Fusion Reactors

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

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

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

Modelling of Water Ingress in to Vacuum Vessel

2014 ◽  
Author(s):  
Tadas Kaliatka ◽  
Eugenijus Ušpuras ◽  
Algirdas Kaliatka
Keyword(s):  
Cooling System ◽  
Nuclear Fusion ◽  
Full Range ◽  
Water Evaporation ◽  
Experimental Investigations ◽  
Fusion Reactors ◽  
Vacuum Vessel ◽  
Temperature Plasma ◽  
Hydraulic Processes ◽  
Relap5 Code

An event of water coolant ingress into vacuum vessel is one of the most important events leading to severe consequences in nuclear fusion reactors. The ingress of coolant to the vacuum vessel could appear due to coolant pipe rupture of in-vessel components. Vacuum vessel could not withstand the high pressure inside. Pressure increase in vacuum vessel is due to water evaporation because of pressure difference and water contact with high temperature plasma facing components. If pressure in vacuum vessel is too high — safety valve opens and the steam containing activated dust will be transferred form the vacuum vessel to the environment. Therefore, it is important to understand the thermo hydraulic processes in vacuum vessel during the ingress of coolant event (ICE). There are few experimental investigations performed, modeling of ICE. In this article ingress of coolant event in vacuum vessel was modeled using RELAP5 code. RELAP5 is a “best estimate” system code suitable for the thermo-hydraulic analysis of all transients and postulated accidents in nuclear fission, light water reactor systems, including both large and small-break loss-of-coolant accidents as well as the full range of operational transients. The use of RELAP5 code for the accident analysis in nuclear fusion reactors allows to perform integral analysis of thermal-hydraulic processes in the cooling system and vacuum vessel. The comparisons of calculation results and experimental data showed that with some limitations the RELAP5 program could be used for the analysis of the thermal hydraulic processes in the vacuum vessel during ICE.

Laser in vessel-viewing system for nuclear fusion reactors

2000 ◽  
Author(s):  
Luciano Bartolini ◽  
Andrea Bordone ◽  
Alberto Coletti ◽  
Mario Ferri De Collibus ◽  
Giorgio G. Fornetti ◽  
...  
Keyword(s):  
Nuclear Fusion ◽  
Fusion Reactors

Synthesis of LiAl2xO2 with Other Transition Metals for Tritium Release in Nuclear Fusion Reactors

2016 ◽  
Vol 8 (1) ◽  
pp. 103-106
Author(s):  
Sung Pil Woo ◽  
In Yea Kim ◽  
Woo Young Lee ◽  
Young Soo Yoon
Keyword(s):  
Transition Metals ◽  
Nuclear Fusion ◽  
Fusion Reactors ◽  
Tritium Release

Comprehensive Safety Analysis Code System for Nuclear Fusion Reactors IV: Preliminary Estimation of Dust Production Due to Plasma Disruptions

1996 ◽  
Vol 30 (1) ◽  
pp. 95-103 ◽  
Author(s):  
Takuro Honda ◽  
Takashi Okazaki ◽  
Yasushi Seki ◽  
Isao Aoki ◽  
Tomoaki Kunugi
Keyword(s):  
Nuclear Fusion ◽  
Safety Analysis ◽  
Fusion Reactors ◽  
Code System ◽  
Dust Production ◽  
Preliminary Estimation
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