Extended plasma source for short-wavelength amplifiers

1978 ◽  
Vol 3 (2) ◽  
pp. 40 ◽  
Author(s):  
J. F. Reintjes ◽  
R. H. Dixon ◽  
R. C. Elton
2021 ◽  
Vol 11 (12) ◽  
pp. 5358
Author(s):  
Ju-Hong Cha ◽  
Sang-Woo Kim ◽  
Ho-Jun Lee

For a conventional linear microwave plasma source (LMPS) with a quasi-coaxial line transverse electromagnetic (TEM) waveguide, a linearly extended plasma is sustained by the surface wave outside the tube. Due to the characteristics of the quasi-coaxial line MPS, it is easy to generate a uniform plasma with radially omnidirectional surfaces, but it is difficult to maximize the electron density in a curved selected region. For the purpose of concentrating the plasma density in the deposition area, a novel LMPS which is suitable for curved structure deposition has been developed and compared with the conventional LMPS. As the shape of a circular waveguide, it is filled with relatively high-permittivity dielectric instead of a quasi-coaxial line waveguide. Microwave power at 2.45 GHz is transferred to the plasma through the continuous cylindrical-slotted line antenna, and the radiated electric field in the radial direction is made almost parallel to the tangential plane of the window surface. This research includes the advanced 3D numerical analysis and compares the results with the experiment. It shows that the electron density in the deposition area is higher than that of the conventional quasi-coaxial line plasma MPS.


2021 ◽  
Vol 16 (12) ◽  
pp. C12019
Author(s):  
G. Marcer ◽  
M. Nocente ◽  
L. Giacomelli ◽  
G. Gorini ◽  
E. Perelli Cippo ◽  
...  

Abstract The fusion power produced in a DT thermonuclear reactor is currently determined by measuring the absolute 14 MeV neutron yield of the D(T, α)n fusion reaction. Measurements of 17 MeV gamma rays born from the much less probable D(T, 5He)γ reaction (branching ratio of ∼10−5) have been proposed as an alternative independent method to validate the neutron counting method and also to fulfill the requests of the nuclear regulator for licensing ITER DT operations. However, the development of absolute 17 MeV gamma ray emission measurements entails a number of requirements, such as: (i) knowledge of the 17 MeV gamma ray to 14 MeV neutron emission branching ratio; (ii) the simulation of the gamma ray transport from the extended plasma source to the gamma ray detectors; (iii) a careful determination of the absolute efficiency of previously calibrated gamma ray spectrometers. In this work, we have studied the possibility to infer the global gamma ray emission rate from measurements made with a 3″ × 6″ LaBr3 spectrometer installed at the end of a collimated tangential line of sight at the JET tokamak and using the neutron emission from deuterium plasmas of the most recent experimental campaigns. Results show that 17 MeV gamma ray fluxes at the end of this tangential line of sight have a weak dependence (less than 5%) on the plasma profile and can therefore be used to infer the total emission from the plasma.


1991 ◽  
Vol 58 (23) ◽  
pp. 2619-2621 ◽  
Author(s):  
W. Hartmann ◽  
H. Bauer ◽  
J. Christiansen ◽  
K. Frank ◽  
H. Kuhn ◽  
...  

2021 ◽  
Vol 7 (2) ◽  
pp. 97-101
Author(s):  
Vladimir V. Knyshev ◽  
Aleksandr G. Karengin ◽  
Igor V. Shamanin

Materials have been selected for the shim rods and burnable absorbers to compensate for the excessive reactivity of the facility’s blanket part and to provide for the possibility of reactivity control in conjunction with a plasma source of neutrons. Burnable absorber is a layer of zirconium diboride (ZrB2) with a thickness of 100 μm applied to the surface of fuel compacts. Boron carbide (B4C) rods installed in the helium flow channels and used to bring the entire system into a state with keff = 0.95 have been selected as the shim rod material. Throughout its operating cycle, the facility is subcritical and is controlled using the neutron flux from the plasma source. Verified codes, WIMS-D5B (ENDF/B-VII.0) and MCU5TPU (MCUDВ50), as well as a modern system of constants were used for the calculations. The facility’s neutronic performance was simulated with regard for the changes in the inner structure and temperature of the microencapsulated fuel and fuel compact materials caused by long-term irradiation and by the migration of fission fragments and gaseous chemical compounds.


1999 ◽  
Vol 116-119 ◽  
pp. 552-557 ◽  
Author(s):  
M. Kaiser ◽  
K.-M. Baumgärtner ◽  
A. Schulz ◽  
M. Walker ◽  
E. Räuchle

2013 ◽  
Vol 20 (3) ◽  
pp. 032103 ◽  
Author(s):  
E. E. Scime ◽  
J. Carr ◽  
M. Galante ◽  
R. M. Magee ◽  
R. Hardin

1979 ◽  
Vol 40 (C7) ◽  
pp. C7-479-C7-480 ◽  
Author(s):  
V. G. Dudnikov ◽  
G. I. Fiksel'

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