Design, Development and Recent Experiments at the CIMPLE-PSI Device
- 1. CIMPLE-PSI Laboratory, Centre of Plasma Physics – Institute for Plasma Research (CPP-IPR), Nazirakhat, Assam (India)
- 2. Institute for Plasma Research (IPR), Bhat, Gandhinagar (India)
- 3. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 St. Paul lez Durance (France)
Description
Full text: It is important to understand how the plasma with unparalleled heat (∼ 10 MW/m2) and ion (∼ 1024/m2s1) flux will interact with the tungsten walls in the ITER tokamak, more specifically at the divertor region of the fusion machine. Several linear magnetized plasma devices have been developed worldwide that reproduced ITER divertor like extreme conditions for studies on relevant plasma surface interaction (PSI) issues under simulated plasma conditions. The "CPP-IPR Magnetized Linear Divertor Plasma Experiment for Plasma Surface Interaction" or CIMPLE-PSI is one of the few Tokamak divertor simulator devices that successfully reproduces both ITER-like ion and heat flux values, whose design, development and recent commissioning will be presented in this paper. Asegmented plasma torch produced high-density plasma jet collimated with a maximum 0.45 T axial magnetic field propagates at few Pascal chamber pressure that is maintained by four numbers of roots vacuum pumps with 14 000 m3 /h pumping capacity that interacts with a remotely placed tungsten target under controlled experimental conditions. The paper will report detailed diagnostics of the plasma jet through optical emission spectroscopic techniques (1.33 m McPherson spectrometer), a retractable Langmuir probe and water calorimeters while operating the plasma with helium and hydrogen mixture of gases. During recent PSI experiments in this device under irradiation of pure helium plasma (exposed for 1800 s under 0.3 T magnetic field, target biased to -45 V), we had witnessed (FESEM, HRTEM) formation of surface nanotendrils in profuse amounts, recent characterization results from which also will be presented here. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
- Imprint Pagination
- 844 p.
- Journal Page Range
- p. 154
- Report number
- IAEA-CN--258
Conference
- Title
- 27. IAEA Fusion Energy Conference
- Acronym
- FEC 2018
- Dates
- 22-27 Oct 2018
- Place
- Ahmedabad (India)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50050340
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALORIMETERS; DESIGN; DIVERTORS; HEAT FLUX; HYDROGEN; IRRADIATION; ITER TOKAMAK; LANGMUIR PROBE; MAGNETIC FIELDS; PLASMA DENSITY; PLASMA JETS; SIMULATION; SIMULATORS; SPECTROMETERS; SURFACES; TRANSMISSION ELECTRON MICROSCOPY; TUNGSTEN; VACUUM PUMPS
- Descriptors DEC
- ANALOG SYSTEMS; CLOSED PLASMA DEVICES; ELECTRIC PROBES; ELECTRON MICROSCOPY; ELEMENTS; EQUIPMENT; FUNCTIONAL MODELS; LABORATORY EQUIPMENT; MEASURING INSTRUMENTS; METALS; MICROSCOPY; NONMETALS; PROBES; PUMPS; REFRACTORY METALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENTS
Optional Information
- Secondary number(s)
- IAEA-CN--258-441