ANIMMA 2021

Session

03 Fusion Diagnostics and Technology

Jun 23, 2021, 2:00 PM

3rd floor (Clarion Congress Hotel Prague)

Conveners

03 Fusion Diagnostics and Technology

• Ludo VERMEEREN (SCK CEN)
• Sylvain GIRARD (Saint-Etienne University)

03 Fusion Diagnostics and Technology: Parallel Intensive Oral Sessions

• Rastislav HODÁK (IEAP CTU in Prague)
• Laurent OTTAVIANI (Aix Marseille Univ, Université de Toulon, CNRS, IM2NP, Marseille, France)

Description

Oral Session

Presentation materials

ZOOM link - 03 Fusion Diagnostics and Technology (23/06)

ZOOM link - Parallel Intensive Oral Sessions - VIRGO (24/06)

251. #03-251 Long Term Neutron Activation in JET DD Operation

ŽOHAR, Andrej (Jožef Stefan Institute)

6/23/21, 2:00 PM

03 Fusion Diagnostics and Technology

Oral presentation

The Joint European Torus (JET) is the largest operating fusion tokamak in the world. This allows performance of unique experiments that cannot be performed anywhere else. One such experiment is long term irradiation of different fusion relevant materials with neutrons produced in deuterium-deuterium (DD) and deuterium-tritium (DT) plasmas. During the last DD plasma campaign at JET in 2019 and...

242. #03-242 In-situ gamma irradiation testing of radiation hardened chips till 1MGy

GEYS, David (Magics Instruments, Belgium)

6/23/21, 2:20 PM

03 Fusion Diagnostics and Technology

Oral presentation

Most of today’s commercial off-the-shelf (COTS) electronics are not specified to meet the demanding requirements of advanced nuclear applications requiring MGy-level TID tolerance. Examples are maintenance and diagnostics tasks in future burning plasma fusion reactors, for example the ITER. Applications such as interventions during nuclear accidents, dismantling of old nuclear power plants and...

134. #03-134 Fusion fuel ion ratio measurements at JET using neutron spectroscopy

ERIKSSON, Benjamin (Uppsala University)

6/23/21, 2:40 PM

03 Fusion Diagnostics and Technology

Oral presentation

The fuel ion ratio, $n_T/n_D$, is an important plasma parameter in magnetically confined fusion, especially for future fusion devices (ITER, DEMO), which plan to achieve fusion through deuterium-tritium (DT) plasmas. In order to maximize the fusion power output, it is necessary to ensure equal number densities of tritium and deuterium (i.e. $n_T/n_D=1$). Neutron spectroscopy offers the...

94. #03-94 Designed A Real-time Full-Range Digitizer for Neutron Flux Monitor On EAST

YANG, Li (Institute of Plasma Physics, Hefei Institutes of Physical Science, Chinese Academy of Science)

6/23/21, 3:00 PM

03 Fusion Diagnostics and Technology

Oral presentation

The neutron flux monitor (NFM) is a standard diagnostic for fusion neutron yield measurement on experimental advanced superconduct tokamak (EAST), and the neutron yield is a most important parameter to research of plasma auxiliary heating. After the upgrade of EAST, higher requirements for neutron flux measurements are put forward. Based on fast ADC (14bit, 500MSPS) and a high-performance...

79. #03-79 Metrology of acquisition chains and signal processing of LMJ experiments

TRAUCHESSEC, Vincent (CEA)

6/23/21, 3:20 PM

03 Fusion Diagnostics and Technology

Oral presentation

Since the first experiment in 2014, more and more plasma diagnostics are being deployed on the Laser MégaJoule (LMJ) facility manufactured by CEA/DAM. These diagnostics aim at measuring radiations or particles emitted during laser experiments to study high-energy physics, especially inertial confinement fusion (ICF). Up to 176 laser beams, converging on a millimeter-sized target placed at the...

162. #03-162 Data acquisition system prototype of the ITER diagnostic Divertor Neutron Flux Monitor testing at research nuclear facilities

MARTAZOV, Evgeny (National Research Nuclear University MEPhI)

6/24/21, 4:20 PM

03 Fusion Diagnostics and Technology

Poster

The Divertor Neutron Flux Monitor is the one of the neutron diagnostics of the International Thermonuclear Experimental Reactor ITER. This diagnostic consists of three subsystems. Each subsystem consists of the detector module includes six fission chambers and the data acquisition system. Detector modules are placed on the inner shell of ITER Vacuum Vessel under the Divertor Cassette. Expected...

139. #03-139 Design of Real-Time Electronics System for Two-Dimensional Hard X-Ray Diagnostics with Intensity Imaging and Energy Spectrum in EAST

CAO, Hongrui (Institute of Plasma Physics, Hefei Institutes of Physical Science), WU, Guo Bin (Hefei University of Technology)

6/24/21, 4:25 PM

03 Fusion Diagnostics and Technology

Poster

Hard X-ray diagnosis is the most important diagnostic in Experimental Advanced Superconducting Tokamak (EAST) for studying low-hybrid wave physics and fast electrons, which helps to improve the operating performance and guarantee the operation safety of EAST Tokamak. The Hard X-Ray diagnostics used 16×16-channels pixel array Cadmium Zinc Telluride (CZT) detector which has the features of high...

110. #03-110 Development of a real-time signal processing unit for diamond detectors of ITER Vertical Neutron Camera

ZHURAVLEV, Michael (Institution "Project Center ITER")

6/24/21, 4:30 PM

03 Fusion Diagnostics and Technology

Poster

Diamond detectors are going to be used in ITER neutron diagnostics, including the Vertical Neutron Camera (VNC). They are meant for neutron flux measurements and measurements of the energy spectrum of fast neutrons.
One of the main functions of VNC is measurement of the neutron source profile. In accordance with ITER requirements VNC has to calculate an updated neutron source profile each...