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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!显示文摘 | Giulio Scocchi Paola Posocco Andrea Danani Sabrina Pricl Maurizio Fermeglia | 2007 | Fluid Phase Equilibria2007，，1： | 1 |
| 3 | 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 |
| 4 | 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 |
| 5 | Linear atrophoderma of Moulin: postulation of mosaicism for a predisposing gene 显示文摘 | Danani R Bittar M Happle R | 2003 | JAm Acad Derma- tol2003，49，3： | 1 |
| 6 | 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 |
| 7 | Multivalent interacting glycodendrimer to prevent amyloid-peptide fibril formation induced by Cu(II): A multidisciplinary approach显示文摘Cu (II ) 离子导致的淀粉的肽 fibrillogenesis 是在 Alzheimers 疾病的致病的一个关键事件。Dendrimers 被发现了在阻止纤丝形成活跃。因此,他们为 Alzheimers 疾病的治疗保持诺言。在这研究,淀粉的肽的纤维性颤动机制 A 1-40 被在 4 th 产生( propyleneimine ) poly ,有硫酸盐的 glycodendrimer functionalized 组织用散布的动态光( DLS ),圆形的二色性( CD ),荧光,电子顺磁的回声( EPR )( MD )并且分子的建模。glycodendrimer 对 mHippoE-18 无毒胚胎的老鼠海马趾的房间,作为一个神经房间模型选择了,并且减少在 Cu (II ) 的增加以后形成的肽总数的毒性。Cu (II )-glycodendrimer, Cu (II )-peptide, 和 glycodendrimer 肽的二进制系统首先被描绘。在最低 Cu (II )/glycodendrimer 臼齿的比率, Cu (II ) 是由 internal-dendrimer 氮地点的 complexed。在这些地点的浸透以后,与硫酸盐组一起的 Cu (II ) 绑定发生了。在 5 min 以内形成并且为从一个螺旋的转变负责到 1-40 的表符合构造的稳定的 Cu (II ) 肽建筑群。Glycodendrimer 肽相互作用挑起了由 Thioflavin T 试金当 Cu (II ) 不在时示威了的 -helix, 的稳定,并且面对由 CD, EPR,和 MD 的 Cu (II ) 。纤丝的形成是 glycodendrimer 和 Cu (II ) 集中为 1-40 的固定数量调制的差别。因此,这多学科的研究便于允许 glycodendrimer 避免 Cu (II ) 导致的纤丝形成的最佳的试验性的条件的识别。 | Anna Janaszewska Barbara Klajnert-Maculewicz Monika MarcinkowskaI Piotr Duchnowicz Dietmar Appelhans Gianvito Grasso Marco A. Deriu Andrea Danani Michela Cangiotti Maria Francesca Ottaviani | 2018 | Nano Research2018，11，3： | 1 |
| 8 | 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 |
| 9 | Thermal- hydraulic and Thermo-structural Analysis of First Wall for Indian DEMO Blanket Module 显示文摘 | CHAUDHURI P DANANI C CHAUDHARI V | 2009 | Fusion Engineering and Design2009，84，26： | 1 |
| 10 | Preliminary Design of Indian Test Blanket Module for ITER显示文摘 | KUMAR E R DANANI C SANDEEP I | 2008 | Fusion Engineering and Design2008，83，79： | 1 |
| 11 | Thermal-hydraulic and thermo-structural analysis of first wall for Indian DEMO blanket module显示文摘 | Paritosh Chaudhuri Chandan Danani Vilas Chaudhari | 2009 | Fusion Engineering and Design2009，84，57： | 1 |
| 12 | 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 |
| 13 | Climate Change and Biodiversity in West Africa Sahel: A Review显示文摘Climate change has many effects on biodiversity.Few studies have focused on the consequences of climate change on biodiversity in West Africa Sahel which is one of the most sensitive regions to climate change.Thus,this study examined the different effects of climate change on biodiversity in West Africa Sahel to guide climate policies.The authors used Google Scholar,Mendeley,ResearchGate,Science-direct,and selected websites of institutions in West Africa and the Sahel for the literature review,with selected keywords in French and English via Boolean operators from 2000 to 2022.The results identified many manifestations of climate change such as drought,lightning,floods,high winds,heavy rains,diseases,extreme heat,and conflicts that affect living things in terrestrial and aquatic ecosystems in these regions.For example,15,000 animals died in Niger and 26,000 in Mali due to flood-related events.In Burkina,41 people died,112 injured,and 12,378 households were left homeless in 13 regions.In Senegal,water stress in the basin is increasingly close to 5,800 m^(3) per person per year.Demographic pressure and planned irrigation projects along Niger and Senegal Rivers have resulted in a significant 25%-60%decline in flows over the past 30 years,causing increasingly severe low flows,frequent interruptions in water flows,drying up of reservoirs and reduced water supply to cities.Rainwater harvesting,afforestation,soil fertility regeneration practices and crop diversification are some biodiversity restoration activities limiting climate change effects in the Sahelian countries of West Africa.These practices have contributed to strengthening the resilience of ecosystems in most of communities.However,priority should be given to policies that raise communities’awareness on the importance of biodiversity conservation and take sustainable and innovative measures to deal with the consequences of floods,droughts,and heat waves,which are the most severe. | Gnanki Mariam Lafia N’gobi Kalamboli Danani Moussa Soulé | 2022 | Research in Ecology2022，4，3： | 0 |
| 14 | Comparative studies for two different orientations of pebble bed in an HCCB blanket显示文摘The Indian Test Blanket Module(TBM) program in ITER is one of the major steps in its fusion reactor program towards DEMO and the future fusion power reactor vision. Research and development(R&D) is focused on two types of breeding blanket concepts: lead–lithium ceramic breeder(LLCB) and helium-cooled ceramic breeder(HCCB) blanket systems for the DEMO reactor. As part of the ITER-TBM program, the LLCB concept will be tested in one-half of ITER port no. 2, whose materials and technologies will be tested during ITER operation. The HCCB concept is a variant of the solid breeder blanket, which is presently part of our domestic R&D program for DEMO relevant technology development. In the HCCB concept Li_2TiO_3 and beryllium are used as the tritium breeder and neutron multiplier, respectively, in the form of a packed bed having edge-on configuration with reduced activation ferritic martensitic steel as the structural material. In this paper two design schemes, mainly two different orientations of pebble beds, are discussed. In the current concept(case-1), the ceramic breeder beds are kept horizontal in the toroidal–radial direction. Due to gravity, the pebbles may settle down at the bottom and create a finite gap between the pebbles and the top cooling plate, which will affect the heat transfer between them. In the alternate design concept(case-2), the pebble bed is vertically(poloidal–radial) orientated where the side plates act as cooling plates instead of top and bottom plates. These two design variants are analyzed analytically and 2 D thermal-hydraulic simulation studies are carried out with ANSYS, using the heat loads obtained from neutronic calculations.Based on the analysis the performance is compared and details of the thermal and radiative heat transfer studies are also discussed in this paper. | Paritosh CHAUDHURI Chandan DANANI E RAJENDRAKUMAR | 2017 | Plasma Science and Technology2017，19，12： | 0 |
| 15 | Preliminary performance analysis and optimization based on 1D neutronics model for Indian DEMO HCCB blanket显示文摘India,under its breeding blanket R&D program for DEMO,is focusing on the development of two tritium breeding blanket concepts;namely the lead-lithium-cooled ceramic breeder and the helium-cooled ceramic breeder(HCCB).The study presented in this paper focuses on the neutronic design analysis and optimization from the tritium breeding perspective of the HCCB blanket.The Indian concept has an edge-on configuration and is one of the variants of the helium-cooled solid breeder blanket concepts proposed by several partner countries in ITER.The Indian HCCB blanket having lithium titanate(Li2TiO3)as the tritium breeder and beryllium(Be)as the neutron multiplier with reduced-activation ferritic/martensitic steel structure aims at utilizing the low-energy neutrons at the rear part of the blanket.The aim of the optimization study is to minimize the radial blanket thickness while ensuring tritium self-sufficiency and provide data for further neutronic design and thermal-hydraulic layout of the HCCB blanket.It is found that inboard and outboard blanket thicknesses of 40 cm and 60 cm,respectively,can give a tritium breeding ratio(TBR)>1.3,with 60%6Li enrichment,which is assumed to be sufficient to cover potential tritium losses and associated uncertainties.The results also demonstrated that the Be packing fraction(PF)has a more profound impact on the TBR as compared to 6Li enrichment and the PF of Li2TiO3. | D AGGARWAL C DANANI M Z YOUSSEF | 2020 | Plasma Science and Technology2020，22，8： | 0 |
| 16 | Neutronic analysis of Indian helium-cooled solid breeder tritium breeding module for testing in ITER显示文摘India has proposed the helium-cooled solid breeder blanket concept as a tritium breeding module to be tested in ITER.The module has lithium titanate for tritium breeding and beryllium for neutron multiplication.Beryllium also enhances tritium breeding.A design for the module is prepared for detailed analysis.Neutronic analysis is performed to assess the tritium breeding rate,neutron distribution,and heat distribution in the module.The tritium production distribution in submodules is evaluated to support the tritium transport analysis.The tritium breeding density in the radial direction of the module is also assessed for further optimization of the design.The heat deposition profile of the entire module is generated to support the heat removal circuit design.The estimated neutron spectrum in the radial direction also provides a more in-depth picture of the nuclear interactions inside the material zones.The total tritium produced in the HCSB module is around 13.87 mg per full day of operation of ITER,considering the 400 s ON time and 1400 s dwell time.The estimated nuclear heat load on the entire module is around 474 kW,which will be removed by the high-pressure helium cooling circuit.The heat deposition in the test blanket model(TBM)is huge(around 9 GJ)for an entire day of operation of ITER,which demonstrates the scale of power that can be produced through a fusion reactor blanket.As per the Brayton cycle,it is equivalent to 3.6 GJ of electrical energy.In terms of power production,this would be around 1655 MWh annually.The evaluation is carried out using the MCNP5 Monte Carlo radiation transport code and FEDNL 2.1 nuclear cross section data.The HCSB TBM neutronic performance demonstrates the tritium production capability and high heat deposition. | H L SWAMI Deepak SHARMA C DANANI P CHAUDHARI R SRINIVASAN Rajesh KUMAR | 2022 | Plasma Science and Technology2022，24，6： | 0 |
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