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| 1 | Activation characteristics of candidate structural materials for a near-term Indian fusion reactor and the impact of their impurities on design considerations显示文摘Activation analyses play a vital role in nuclear reactor design.Activation analyses,along with nuclear analyses,provide important information for nuclear safety and maintenance strategies.Activation analyses also help in the selection of materials for a nuclear reactor,by providing the radioactivity and dose rate levels after irradiation.This information is important to help define maintenance activity for different parts of the reactor,and to plan decommissioning and radioactive waste disposal strategies.The study of activation analyses of candidate structural materials for near-term fusion reactors or ITER is equally essential,due to the presence of a highenergy neutron environment which makes decisive demands on material selection.This study comprises two parts; in the first part the activation characteristics,in a fusion radiation environment,of several elements which are widely present in structural materials,are studied.It reveals that the presence of a few specific elements in a material can diminish its feasibility for use in the nuclear environment.The second part of the study concentrates on activation analyses of candidate structural materials for near-term fusion reactors and their comparison in fusion radiation conditions.The structural materials selected for this study,i.e.India-specific Reduced Activation Ferritic-Martensitic steel(IN-RAFMS),P91-grade steel,stainless steel 316 LN ITER-grade(SS-316 LN-IG),stainless steel 316 L and stainless steel 304,are candidates for use in ITER either in vessel components or test blanket systems.Tungsten is also included in this study because of its use for ITER plasma-facing components.The study is carried out using the reference parameters of the ITER fusion reactor.The activation characteristics of the materials are assessed considering the irradiation at an ITER equatorial port.The presence of elements like Nb,Mo,Co and Ta in a structural material enhance the activity level as well as the dose level,which has an impact on design considerations.IN-RAFMS was shown to be a more effective low-activation material than SS-316 LN-IG. | H L SWAMI C DANANI A K SHAW | 2018 | Plasma Science and Technology2018，20，6： | 2 |
| 2 | To the nanoscale, and beyond! Multiscale molecular modeling of polymer-clay n anocomposites显示文摘 | Scoocchi G Posocco E Danani A | 2007 | Fluid Phase Equilibia2007，261，： | 1 |
| 3 | Training of the position controller in SST-1 using TSC simulations显示文摘 | I Bandyopadhyay D Raju A Balakrishnan R.K Bandyopadhyay C Danani S.P Deshpande R Srinivasan | 2004 | Fusion Engineering and Design2004，，3： | 1 |
| 4 | 查看详情显示文摘 | Jensen L B Pavan G M Kasimova M R Rutherford S Danani A Nielsen H M Foged C | | 0，，02： | 1 |
| 5 | Homology and moleculardynamics models of Toll-like receptor 7 protein and its dimefization 显示文摘 | Tseng CY Gajewski M Danani A | 2014 | Chem Biol Drug Des2014，83，6： | 1 |
| 6 | A neutronic experiment to support the design of an Indian TBM shield module for ITER显示文摘A shield module is associated with an Indian Test Blanket Module (TBM) in ITER to limit the radiation doses in port inter-space areas.The shield module is made of stainless steel plates and water channels.It is identified as an important component for radiation protection because of its radiation exposure control functionality.The radiation protection classification leads to more assurance of the component design.In order to validate and verify the design of the shield module,a neutronic laboratory-scale experiment is designed and executed.The experiment is planned by considering the irradiation under a neutron source of 14 MeV and yields of 1010 n s-1.The reference neutron spectrum of the ITER TBM shield module has been achieved through optimization of the neutron source spectrum by a combination of steel and lead materials.The neutron spectrum and flux are measured using a multiple foil activation technique and neutron dose-rate meter LB 6411 (He-3 proton recoil counter with polyethylene),respectively.The neutronic design simulation is assessed using MCNP5 and FENDL 2.1 crosssection data.The paper covers neutronic design,irradiation and the outcome of the experiment in detail. | H L SWAMI M ABHANGI Sanchit SHARMA S TIWARI A N MISTRY V VASAVA V MEHTA S VALA C DANANI V CHAUDHARI P CHAUDHURI | 2019 | Plasma Science and Technology2019，21，6： | 1 |
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