Inner Frozen Metal Blanket Concept for an ICF Reactor
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概要
- 論文の詳細を見る
A new blanket concept for an inertial confinement fusion (ICF) reactor is proposed for protecting the structural materials from the impact of X-rays and plasma and controlling the plasma expansion. The inner blanket consists of several cm of frozen metal with holes for entry of the laser beams and for blow-off of the plasmas. The inner blanket is injected from the top of the reactor chamber at a speed of about 50 m/s. It is located near the fuel pellet (〜 10 cm from the pellet and 〜 5 m from the structural materials). When a microexplosion occurs, the inner frozen metal blanket is melted by the neutron heating and falls into the liquid metal pool, expanding and being guided by the magnetic field. The performance and neutronics calculations of the inner blanket are presented here using a simple model.
- 社団法人応用物理学会の論文
- 1983-06-20
著者
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Ido Shunji
Institute Of Laser Engineering Osaka University
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TSUJI Ryusuke
Institute of Laser Engineering, Osaka University
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Tsuji Ryusuke
Institute Of Laser Engineering Osaka University
関連論文
- Ignition and Burning Calculations in Inertial Confinement Fusion Driven by Light Ion Beam
- Pellet Gain Optimization of Particle Beam Fusion with Au Shell and DT Fuel Target
- Computer Simulation of Nonlinear Propagation Characteristics of CO_2 Laser Pulse
- Two Secondary Fusion Reactions in Deuterium Fuel as a Diagnostic for Fuel-Pusher Mixing Rate in Inertial Confinement Fusion
- Measurement of ICF Plasma Parameters by the Activation Method
- A Pellet Model of DT Ignitor and DD Fuel for an ICF Reactor without Tritium Breeding Blanket
- Inner Frozen Metal Blanket Concept for an ICF Reactor
- Implosion Efficiency of Light Ion Beam Driven Target
- Nuclear Analysis of GEKKO XII ICF Experiment Facility
- Cryogenic Neutron Calorimeter for and ICF Test Facility
- Neutronics calculations in pellets and blankets of laser fusion reactor concept SENRI-I.