Skip to main content

Currently Skimming:

TECHNOLOGICAL CONSIDERATIONS OF D-T FUSION
Pages 17-23

The Chapter Skim interface presents what we've algorithmically identified as the most significant single chunk of text within every page in the chapter.
Select key terms on the right to highlight them within pages of the chapter.


From page 17...
... The technological requirements associated with power handling in a fusion reactor depend on the confinement scheme. The Tokamak Reactor Concept The Tokamak reactor operates in an ignited, quasi-steady-state mode.
From page 18...
... Inertial energy storage could also be used in reactors, but inductive energy storage and homopolar generators are also being investigated for Tokamak applications. It is generally assumed that the intrinsic ohmic heating process in Tokamaks will not provide sufficient heating to bring the plasma up to the ignition temperature and therefore auxiliary heating will be required to achieve ignition.
From page 19...
... The energy required to start up and sustain the plasma burn would be provided by neutral beam injectors that would also serve as the fuel source in reactors. For mirror reactors operating with classical confinement (Q*
From page 20...
... The enhancement of Q in mirror-based devices has become a major objective of the mirror program and is being pursued vigorously both at the Lawrence Livermore Laboratory and at the Oak Ridge National Laboratory. The Inertial-Confinement Reactor Concept In this concept, plasma heating energy in the form of laser beams, electron beams, or ion beams is delivered to a fuel pellet in about l nanosecond (l0~9s)
From page 21...
... Energy deposition at the first wall of the blanket will result in design limitations based on thermal stress considerations for all reactor concepts. The potential effects of energy deposition at the first wall appear to be most severe in the case of inertial confinement.
From page 22...
... It appears that the erosion processes of potential concern in fusion reactors will be plasma-particle sputtering and exfoliation resulting from the bursting of radiation-induced blisters. Currently, these phenomena are poorly understood in the context of a fusion reactor environment and, therefore, it is not possible to calculate accurate surface erosion rates in fusion reactors at present.
From page 23...
... Therefore, an extensive experimental program will be required to define the corrosion behavior of potential structural materials in lithium, lithium salts, and helium under the operating conditions and radiation environment expected in fusion reactors.


This material may be derived from roughly machine-read images, and so is provided only to facilitate research.
More information on Chapter Skim is available.