A5038260422- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Radiation Detection and Scintillator Technologies
- Nuclear physics research studies
- Graphite, nuclear technology, radiation studies
- Silicon and Solar Cell Technologies
- Particle Detector Development and Performance
- Advanced Semiconductor Detectors and Materials
- Ion-surface interactions and analysis
- Radiation Therapy and Dosimetry
- Advanced materials and composites
- Plasma Diagnostics and Applications
- Nuclear materials and radiation effects
- High-Energy Particle Collisions Research
- Nuclear and radioactivity studies
- Silicon Carbide Semiconductor Technologies
- Boron Compounds in Chemistry
- Advanced Materials Characterization Techniques
- Muon and positron interactions and applications
- X-ray Spectroscopy and Fluorescence Analysis
Institute for Plasma Research
2016-2025
Homi Bhabha National Institute
2018-2025
Royal Military Academy
2020
nLIGHT (United States)
2018
Uppsala University
2017
Culham Science Centre
2017
Ball (France)
2014
National Superconducting Cyclotron Laboratory
2014
Michigan State University
2014
Moscow Engineering Physics Institute
2014
The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...
Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...
Because of their desirable structural properties, WC, WC+B4C, and WC + TiC are possible materials for use in plasma-facing components fusion reactors like tokamaks. In this work, seven different compositions WC-W2C composites have been prepared (30 to 50 at. % C) by an arc plasma melting technique followed furnace cooling. Efforts made produce a composite that is very hard tough has high neutron absorbing capacity adding B4C (5 15 wt% each) the starting powder. Microstructures were studied...
The present paper describes the findings of calibration neutron yield monitors on Joint European Torus (JET) performed in 2013 using a 252Cf source deployed inside torus by remote handling system, with particular regard to fission chambers which provide time resolved from JET plasmas. experimental data obtained toroidal, radial, and vertical scans are presented. These first analysed following an analytical approach adopted previous calibrations at JET. In this way, function for volumetric...
We have measured the proton decay probabilities of $^{56}\mathrm{Fe}^{*}$ and $^{47}\mathrm{Ti}^{*}$ compound systems which are populated by transfer reactions $^{52}\mathrm{Cr}(^{6}\mathrm{Li},d)^{56}\mathrm{Fe}^{*}$ (surrogate $n+^{55}\mathrm{Fe}\ensuremath{\rightarrow}^{56}\mathrm{Fe}^{*}\ensuremath{\rightarrow}p+^{55}\mathrm{Mn})$ $^{45}\mathrm{Sc}(^{6}\mathrm{Li},\ensuremath{\alpha})^{47}\mathrm{Ti}^{*}$...
The present study, carried out for the first time, contributes to multidisciplinary work in reactor design and nuclear astrophysics. Cadmium has been chosen study its significant importance development of reactors astrophysical $p$ process. A stacked foil activation technique followed by offline $\ensuremath{\gamma}$-ray spectroscopy were used carry work. Cross sections measured $^{114}\mathrm{Cd}{(p,\ensuremath{\gamma})}^{115m}$ reaction due scarcity data observed literature. $S$ factor was...
Abstract A high energy and yield neutron source is a prime requirement for technological studies related to fusion reactor development. It provides high-energy environment small-scale components research testing such as tritium breeding, shielding, plasma-facing materials, reaction cross-section data study etc. Along with ITER participation, the Institute of Plasma Research, India developing an accelerator-based 14 MeV 10 12 n s −1 . The design based on deuterium–tritium reaction. deuterium...
A shield module is associated with an Indian Test Blanket Module (TBM) in ITER to limit the radiation doses port inter-space areas. The made of stainless steel plates and water channels. It identified as important component for protection because its exposure control functionality. classification leads more assurance design. In order validate verify design module, a neutronic laboratory-scale experiment designed executed. planned by considering irradiation under neutron source 14 MeV yields...
The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct lab scale experiments related Indian breeding blanket system ITER and DEMO. It will also be utilized material testing, shielding development of fusion diagnostics. Occupational radiation exposure control necessary all kind nuclear facilities get operational licensing from governing authorities regulatory bodies. In same way, at occupational worker area accessible zones general...
Abstract In this work, the fabrication, electrical characterization and alpha spectral of single-crystal (SC) diamond bulk radiation detector have been carried out. The performance metrics SC-diamond such as leakage current density, charge collection efficiency, resolution polarization effects are studied compared with a fabricated using High-Pure Semi-Insulating (HPSI) 4H-SiC. It is found that exhibits lower higher μτ product, better no in comparison to HPSI 4H-SiC detector. time response...
Numerical simulation studies of D-T fusion produced neutron irradiation-induced changes in the electrical characteristics commercially available Passivated Implanted Planar Silicon (PIPS) detectors (with ρ = 7.4 kΩcm) are carried out using a commercial device simulator for plasma X-ray tomography nuclear reactors. The proposed radiation damage model is validated by comparing with experimental data 14.1 MeV irradiated PIPS detector fluence up to 3.6 ×10 <sup...