Experimental determination of fuel density‐radius product of inertial confinement fusion targets using secondary nuclear fusion reactions

1986 ◽  
Vol 49 (10) ◽  
pp. 555-557 ◽  
Author(s):  
H. Azechi ◽  
N. Miyanaga ◽  
R. O. Stapf ◽  
K. Itoga ◽  
H. Nakaishi ◽  
...  
Keyword(s):  
Experimental Determination ◽  
Inertial Confinement Fusion ◽  
Nuclear Fusion ◽  
Inertial Confinement ◽  
Fusion Reactions ◽  
Fuel Density ◽  
Confinement Fusion ◽  
Density Radius ◽  
Nuclear Fusion Reactions

Determination of fuel density‐radius product of inertial confinement fusion targets by neutron activation

1980 ◽  
Vol 51 (12) ◽  
pp. 6062-6064 ◽  
Author(s):  
E. M. Campbell ◽  
S. M. Lane ◽  
Y. L. Pan ◽  
J. T. Larsen ◽  
R. J. Wahl ◽  
...  
Keyword(s):  
Neutron Activation ◽  
Inertial Confinement Fusion ◽  
Inertial Confinement ◽  
Fuel Density ◽  
Confinement Fusion ◽  
Density Radius

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 Enhanced Beam of Protons in Plasma Gas for Three Systems (Tokamak, Z-Pinch and ICF)

2015 ◽  
Vol 61 ◽  
pp. 63-76
Author(s):  
Baida M. Ahmed ◽  
Khalid A. Ahmad ◽  
Riayhd K. Ahmad
Keyword(s):  
Inertial Confinement Fusion ◽  
Dispersion Function ◽  
Inertial Confinement ◽  
Small Contribution ◽  
Geometrical Structures ◽  
Plasma Target ◽  
Confinement Fusion ◽  
Work Interaction ◽  
Z Pinch

The interaction of fast beam of proton impinging on a plasma target is treated theoretically, since in general the number density of the beam ions nb is much smaller than the electron density ne of the plasma target. The interaction between proton clusters (collective and individual) with plasma gas is evaluated using the dielectric dispersion function Vlasove formalism both for single and correlated protons.In present work interaction clusters for proton on three different systems (tokamak, Z-pinch and inertial confinement fusion (ICF)) were used at different thermal energy (1000, 20 and 300) (a.u) and densities of proton (1013, 1018 and 3x1022) cm-3 at three velocities (1,7.5 and 35) a.u. to study the effect of these parameters. Found that collective excitations give a small contribution to the energy loss of single ions, We obtain the best beams of the protons in the system (ICF) and at high rates (0,0.2,0.4,0.6) increase with increasing density. This gives a good beam of plasma proton use in different applications such as metal alloying, surface treatment, implantation, surface analysis, sputtering, determination of geometrical structures of polyatomic ions in addition give information about a variety of atomic-collision phenomena.

scholarly journals Performance Optimisation of Inertial Confinement Fusion Codes using Mini-applications

2016 ◽  
Vol 32 (4) ◽  
pp. 570-581
Author(s):  
Robert F Bird ◽  
Patrick Gillies ◽  
Michael R Bareford ◽  
Andy Herdman ◽  
Stephen Jarvis
Keyword(s):  
Inertial Confinement Fusion ◽  
High Performance ◽  
Pulse Shaping ◽  
Inertial Confinement ◽  
Fusion Reactions ◽  
Simulation Code ◽  
Particle In Cell ◽  
Leading Role ◽  
Confinement Fusion ◽  
Successive Generations

Despite the recent successes of nuclear energy researchers, the scientific community still remains some distance from being able to create controlled, self-sustaining fusion reactions. Inertial Confinement Fusion (ICF) techniques represent one possible option to surpass this barrier, with scientific simulation playing a leading role in guiding and supporting their development. The simulation of such techniques allows for safe and efficient investigation of laser design and pulse shaping, as well as providing insight into the reaction as a whole. The research presented here focuses on the simulation code EPOCH, a fully relativistic particle-in-cell plasma physics code concerned with faithfully recreating laser-plasma interactions at scale. A significant challenge in developing large codes like EPOCH is maintaining effective scientific delivery on successive generations of high-performance computing architecture. To support this process, we adopt the use of mini-applications – small code proxies that encapsulate important computational properties of their larger parent counterparts. Through the development of a mini-application for EPOCH (called miniEPOCH), we investigate a variety of the performance features exhibited in EPOCH, expose opportunities for optimisation and increased scientific capability, and offer our conclusions to guide future changes to similar ICF codes.

scholarly journals Synergism in inertial confinement fusion: a total direct energy conversion package

1989 ◽  
Vol 7 (3) ◽  
pp. 449-466 ◽  
Author(s):  
M. A. Prelas ◽  
E. J. Charlson
Keyword(s):  
Energy Conversion ◽  
Inertial Confinement Fusion ◽  
Fusion Reaction ◽  
Inertial Confinement ◽  
Fusion Reactions ◽  
Direct Energy Conversion ◽  
Transport Length ◽  
Confinement Fusion ◽  
Direct Energy ◽  
Energy Conversion Devices

The products of fusion reactions have unique properties which can be used for direct energy conversion. These products are neutrons and ions. Neutrons can be transported very long distances through solid materials and can interact with certain elements which have a very high absorption cross section. Ions on the other hand have a very short transport length even in a gaseous medium. It is possible to utilize these products in an inertial confinement fusion reactor with two different direct energy conversion devices: a nuclear-pumped laser using neutrons from the fusion reaction; a photon generator material combined with a photovoltaic converter using the ionic fusion products.It will be argued that a nuclear-pumped laser can be more efficient than a conventional laser. It will also be shown that an advanced energy conversion concept based on photon production and photovoltaics can produce ICF system efficiencies of 56%.

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