27th IEEE Symposium on Fusion Engineering

Session

R.OP1: Diagnostics and Instrumentation II

R.OP1

8 Jun 2017, 12:40

Marriott Shanghai City Center

370. Neutron Diagnostics in the Large Helical Device

Prof. Mitsutaka Isobe (National Institute for Fusion Science, National Institutes of Natural Sciences, SOKENDAI(The Graduate University for Advanced Studies))

08/06/2017, 12:40

Diagnostics and instrumentation

Oral

Deuterium plasma experiment begins in the Large Helical Device (LHD) in March, 2017 in oder to to explore higher-performance plasmas in LHD and to gain a positive prospect toward an LHD-type fusion reactor. In the operation of LHD, neutron yield measurement is essentially required because neutron yield has to be managed in compliance with permitted neutron budgets. In terms of plasma physics,...

121. Joint plasma pressure diagnostic system of Beam Emission Spectroscopy and Ultrafast Charge eXchange Recombination Spectroscopy on EAST tokamak

Dr Yi Yu (University of Science and Technology of China)

08/06/2017, 13:00

Diagnostics and instrumentation

Oral

In this article we present the development of the joint plasma pressure diagnostic system on EAST tokamak, i.e., the Beam Emission Spectroscopy (BES) and the Ultrafast Charge eXchange Recombination Spectroscopy (UF-CXRS) basing on Neutral Beam Injection which are to diagnose two-dimensional plasma density and ion temperature simultaneously at the same spatial area with a time resolution at the...

172. Estimation of X-mode reflectometry first fringe frequency using neural networks

Mr Diogo E. Aguiam (Instituto de Plasmas e Fusão Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal)

08/06/2017, 13:40

Diagnostics and instrumentation

Oral

One of the main issues with X-mode density profile reflectometry is the correct determination of the upper cut off first fringe reflection.
The propagation of electromagnetic waves in X mode in plasmas is characterized by two cut off frequency regions that depend on the local plasma electron density and the local magnetic field.
By using the upper cut off region for electron density profile...

239. In situ and real time observation of tritium behavior in the metal by reversing associated particle spectra of DT neutron generator

Dr Qingjun Zhu (ASIPP)

08/06/2017, 14:00

Diagnostics and instrumentation

Oral

In the thermonuclear fusion reactor research, the tritium behavior in the metal, including adsorption, desorption, dissolution, diffusion, permeation, was critical to tritium economy and environmental safety, due to most material in the fusion reactor is metal, the tritium-metal interaction is a research focus in this field. The knowledge of the tritium behavior in the metal is a critical...

542. Managing ITER diagnostics and port plug engineering project risks

Mr Russell Feder (Princeton Plasma Physics Laboratory)

08/06/2017, 14:20

Diagnostics and instrumentation

Oral

Risk management is a key part of any successful project. Projects like ITER with high technical challenges and complex integration vitally depend on risk management. This paper will describe the organization and management of risks within the ITER diagnostics and port plug engineering project design phase. A typical risk impacts design-phase cost and schedule due to the need for specific...