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2016 | OriginalPaper | Chapter

1. Thermonuclear Fusion

Author : Begoña Gómez-Ferrer

Published in: Resistivity Recovery in Fe and FeCr alloys

Publisher: Springer International Publishing

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Abstract

The motivation of this work arises from the need of developing new technologies in order to build the future nuclear fusion reactors. Section 1.1 is devoted to provide an overview of fusion energy, showing the interest of its development and the key problems that need to be overcome for this purpose. Section 1.2 introduces specifically the problematic of radiation damage in the constituent materials of fusion reactors. Next, Sect. 1.3 explains the strong commitment of fusion research community in the development of modelling and experimental validation approach, as a useful tool for radiation resistant materials development in the medium term. Finally, Sect. 1.4 introduces the specific interest and problematic of structural materials which can be modelled to a first approximation as binary FeCr_x alloys and which are the object of study of this work.

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next chapter Resistivity and Experimental Techniques

In the future, it has to be noted that there are other reactions, indicated in the text, which use ³He, Li or B and are completely free of radioactivity. Note that lithium and boron are safe and abundant elements.

Gamma radiation is originated in fusion reactors from different processes like:

D + p → ³He + γ (5.5 MeV)
T + p → ⁴He + γ (20 MeV)
D + D → ⁴He + γ (24 MeV)
D + T → ⁵He + γ (17 MeV)
⁹Be + ⁴He → n + ¹²C + γ (4.44 MeV)
¹⁰B + ⁴He → p + ¹³C + y (3.1, 3.7, 3.85 MeV)

+… every nuclear reaction between the generated neutrons with the constituent reactor materials.

Although the real problem due to T leakage would be its inhalation.

In the case of magnetic confinement fusion. Inertial confinement fusion (ICF) is also a developing energy. In ICF reactors D + T ignition will be produced by means of concentration of powerful laser beams in the central point of a vacuum chamber where the fuel pellet will be placed.

Demonstration Power Plant [6].

The model alloys Fe_1−x–Cr_x are the base of the reduced-activation ferritic/martensitic steels which have been chosen as main candidates to build the structure of the first wall in future fusion reactors.

RR is a very specific experimental technique traditionally used to study the mobility and kinetics of simple defects in metals by means of the follow-up of the residual resistivity of a sample along an isochronal step-annealing after irradiation at cryogenic temperatures.

Also liquid breeder blanket technology is being considered as an alternative to solid breeders in future fusion devices.

Although it is more and more accepted in the scientific community that this analogy is not straightforward given the effects of injected interstitials—in swelling and embrittlement—as well as dose rate effects in the evolution of the microstructure.

Nanocomposited oxide-dispersion-strengthened (ODS) ferritic steels.

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Title: Thermonuclear Fusion
Author: Begoña Gómez-Ferrer
Publisher: Springer International Publishing
Book: Resistivity Recovery in Fe and FeCr alloys
Print ISBN: 978-3-319-38856-4

Electronic ISBN: 978-3-319-38857-1

Copyright Year: 2016
DOI: https://doi.org/10.1007/978-3-319-38857-1_1

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