Neutron Activation in First-Wall Materials for Advanced-Fuel Fusion Reactors

1991 ◽  
Vol 19 (3P2A) ◽  
pp. 852-856 ◽  
Author(s):  
Massimo Zucchetti
Keyword(s):  
Neutron Activation ◽  
Fusion Reactors ◽  
First Wall ◽  
Advanced Fuel ◽  
Wall Materials

Transport parameters and permeation behavior of hydrogen isotopes in the first wall materials of future fusion reactors

2020 ◽  
Vol 155 ◽  
pp. 111563
Author(s):  
Yue Xu ◽  
Zuo-Sheng Wu ◽  
Lai-Ma Luo ◽  
Xiang Zan ◽  
Xiao-Yong Zhu ◽  
...  
Keyword(s):  
Hydrogen Isotopes ◽  
Fusion Reactors ◽  
First Wall ◽  
Transport Parameters ◽  
Wall Materials

Low activation first wall materials for fusion reactors

1989 ◽  
Vol 10 ◽  
pp. 463-467
Author(s):  
T. Noda ◽  
F. Abe ◽  
Y. Hiraoka ◽  
H. Araki ◽  
T. Fujii ◽  
...  
Keyword(s):  
Fusion Reactors ◽  
First Wall ◽  
Wall Materials

scholarly journals Development of advanced fuel inertial fusion targets

1997 ◽  
Vol 15 (4) ◽  
pp. 575-587 ◽  
Author(s):  
N.A. Tahir ◽  
D.H.H. Hoffmann
Keyword(s):  
Power Plant ◽  
Neutron Activation ◽  
First Generation ◽  
Fusion Reactor ◽  
Inertial Fusion ◽  
Fusion Reactors ◽  
Low Level ◽  
Environmental Compatibility ◽  
Sufficient Energy ◽  
Advanced Fuel

This paper discusses the implications of using different fuels, including pure deuterium, deuterium–tritium, deuterium–helium3, and proton–boron11, on safety and environmental compatibility of the fusion reactor, as well as on the driver requirements. Due to present-day technology limitations, it seems likely that the first generation of the fusion reactors will be based on a deuterium–tritium cycle. Such a scheme, however, would pose serious problems, including neutron activation and tritium handling. We show that by developing low-level tritium inertial fusion targets, one may substantially reduce the daily use of tritium in the reactor that may ultimately lead to a reduction in the overall tritium inventory in the power plant. Such reduced tritium targets will still generate sufficient energy to run the power plant economically.

scholarly journals Plasma–wall interaction in laser inertial fusion reactors: novel proposals for radiation tests of first wall materials

2012 ◽  
Vol 54 (12) ◽  
pp. 124051 ◽  
Author(s):  
J Alvarez Ruiz ◽  
A Rivera ◽  
K Mima ◽  
D Garoz ◽  
R Gonzalez-Arrabal ◽  
...  
Keyword(s):  
Inertial Fusion ◽  
Fusion Reactors ◽  
First Wall ◽  
Wall Materials ◽  
Wall Interaction

Alignment of small He-Bubbles during in situ deformation of Al-foils

1978 ◽  
Vol 36 (1) ◽  
pp. 396-397
Author(s):  
E. Ruedl ◽  
P. Schiller
Keyword(s):  
Fusion Reactor ◽  
Matrix Material ◽  
Fusion Reactors ◽  
First Wall ◽  
Potential Matrix ◽  
In Situ Deformation ◽  
Α Particles ◽  
Metal Aluminium

The low Z metal aluminium is a potential matrix material for the first wall in fusion reactors. A drawback in the application of A1 is the rel= atively high amount of He produced in it under fusion reactor conditions. Knowledge about the behaviour of He during irradiation and deformation in Al, especially near the surface, is therefore important.Using the TEM we have studied Al disks of 3 mm diameter and 0.2 mm thickness, which were perforated at the centre by double jet polishing. These disks were bombarded at∽200°C to various doses with α-particles, impinging at any angle and energy up to 1.5 MeV at both surfaces. The details of the irradiations are described in Ref.1. Subsequent observation indicated that in such specimens uniformly distributed He-bubbles are formed near the surface in a layer several μm thick (Fig.1).After bombardment the disks were deformed at 20°C during observation by means of a tensile device in a Philips EM 300 microscope.

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