The International Thermonuclear Experimental Reactor (ITER) will use an electron cyclotron resonance heating (ECRH) system in the upper port of the device for plasma stabilization, heating, and current drive by injecting millimeter wave beams into the plasma chamber. The millimeter waves are transmitted to the plasma through long and narrow waveguide channels. The required plasma wall openings could result in enhanced neutron radiation loadings to the ECRH launcher and neighboring reactor components. The analyses aimed at proving that the shielding requirements and all related nuclear design limits specified by ITER can be met for the proposed ECRH launcher design concepts. The nuclear criteria included human safety issues, nuclear waste re...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support...
This thesis discusses the development, benchmarking and applications of activation dose analysis met...
A basic requirement for ITER equipment to meet is a high level of reliability, because ITER operatio...
Computational results of the nuclear analyses for the ECRH launcher integrated into the ITER upper p...
Comprehensive neutronic analyses are being performed for different variants of the International The...
The paper reports the latest achievements in the neutronics modelling of the electron cyclotron reso...
The Divertor Tokamak Test facility (DTT) will be a superconductive machine that aims at studying the...
The structural design of the ECRH Upper Port Plug is developed to in-tegrate mm-wave systems for bot...
Radiation shielding analysis conducted in support of design development of the contemporary diagnost...
The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma ...
The challenge of developing the conceptual design of the ECH Upper Launcher system for MHD control i...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support...
Radiation shielding requirements for fusion reactors present different problems than those for fissi...
This paper elaborates computational challenges tackled for providing neutronics service supplied for...
Four ITER EC H&CD (Electron Cyclotron Heating and Current Drive) Upper Launchers will be install...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support...
This thesis discusses the development, benchmarking and applications of activation dose analysis met...
A basic requirement for ITER equipment to meet is a high level of reliability, because ITER operatio...
Computational results of the nuclear analyses for the ECRH launcher integrated into the ITER upper p...
Comprehensive neutronic analyses are being performed for different variants of the International The...
The paper reports the latest achievements in the neutronics modelling of the electron cyclotron reso...
The Divertor Tokamak Test facility (DTT) will be a superconductive machine that aims at studying the...
The structural design of the ECRH Upper Port Plug is developed to in-tegrate mm-wave systems for bot...
Radiation shielding analysis conducted in support of design development of the contemporary diagnost...
The design of the ITER ECRH system provides 20 MW millimeter wave power for central plasma ...
The challenge of developing the conceptual design of the ECH Upper Launcher system for MHD control i...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support...
Radiation shielding requirements for fusion reactors present different problems than those for fissi...
This paper elaborates computational challenges tackled for providing neutronics service supplied for...
Four ITER EC H&CD (Electron Cyclotron Heating and Current Drive) Upper Launchers will be install...
Neutronics analysis to find nuclear heating rates and personnel dose rates were conducted in support...
This thesis discusses the development, benchmarking and applications of activation dose analysis met...
A basic requirement for ITER equipment to meet is a high level of reliability, because ITER operatio...