energy.materials.ox.ac.uk Report : Visit Site


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    The main IP address: 129.67.87.195,Your server United Kingdom,Oxford ISP:Oxford University  TLD:uk CountryCode:GB

    The description :skip to navigation skip to content energy materials navigation current page is 1: nuclear materials 2: members 3: links 4: available positions 5: meetings 6: nuclear projects energy (nuclear) material...

    This report updates in 25-Aug-2018

Technical data of the energy.materials.ox.ac.uk


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Latitude: 51.752220153809
Longitude: -1.2559599876404
Country: United Kingdom (GB)
City: Oxford
Region: England
ISP: Oxford University

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cname:ext-webs.materials.ox.ac.uk.
ipv4:IP:129.67.87.195
ASN:786
OWNER:JANET Jisc Services Limited, GB
Country:GB

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skip to navigation skip to content energy materials navigation current page is 1: nuclear materials 2: members 3: links 4: available positions 5: meetings 6: nuclear projects energy (nuclear) materials welcome to energy materials introduction the energy materials website is intended to be a gateway to the broad range of energy-related materials research at oxford university, particularly in the materials department. at the present time, it focussed on materials for nuclear fission and nuclear fusion power. the nuclear fission research is aimed at current and next generation plant (including generation iv). many fundamental issues are common to both fission and fusion. atomic scale study of oxide dispersion strengthened steels dislocation network in ods-eurofer 97, before and after ion implantation atomic scale study of oxide dispersion strengthened steels ti-y-o clusters in epfl-14cr-2w-0.3ti & y2o3 ods steel deformation and fracture of concrete microstructures evolution of the compressive damage in a concrete specimen, studied with tomography and digital volume correlation deformation and fracture of concrete microstructures nominal strain field within one 2d slice of a 3d dataset, in which an initiated crack is visible, compared with the microstructure hydride cracking in zirconium triangular cantilever for testing elastic properties hydride cracking in zirconium local misorientation around indents made in pure zr measured using ebsd micromechanical testing of scc behaviour at individual grain boundaries micromechanical test specimen for stress corrosion cracking of a grain boundary powder processing of ods alloys for nuclear applications ods powder milled for 8hours in the planetary ball mill radiation damage in iron-based alloys ion radiation damage in fe 11%cr small scale mechanics applied to nuclear materials fib-milled cantilever in fe the effects of neutron radiation on oxide dispersion strengthened steels a fib lift out with protective platinum layer from helium implanted eurofer 97 oxide dispersion strengthened steel at 1um under focus the effects of neutron radiation on oxide dispersion strengthened steels helium bubbles in eurofer 97 oxide dispersion strengthened steel at 1um under and over focus three-dimensional damage nucleation in energy.materials visualization, via strain mapping, of a crack inside a short-rod, chevron notched poly-granular graphite sample three-dimensional damage nucleation in energy.materials a horizontal slice through the strain field measured within a short-rod, chevron notched poly-granular graphite sample micromechanical modelling dislocation dynamic simulation of micro-cantilever beam mimicking neutron damage in tungsten using self ion implantation atomic force microscope scans of nanoindents in w5wt%ta at differing ion damage levels showing change in pile up structure mimicking neutron damage in tungsten using self ion implantation ion implantation of tungsten 800oc at cea saclay, france mimicking neutron damage in tungsten using self ion implantation ion implantation of tungsten 800oc at cea saclay, france variable temperature nanoindentation array of identical micro-cantilevers for high temperature fracture testing at 750oc powder processing of ods alloys for nuclear applications transmission electron microscopy image of ods powder particle after mechanical alloying for 60 hrs and 1 hr annealing at 700â°c. powder processing of ods alloys for nuclear applications atom probe topography maps from an ods powder particle after mechanical alloying showing a homogeneous distribution of yttrium and chromium throughout the sample volume. powder processing of ods alloys for nuclear applications ebsd image of bulk ods with composition of fe-14cr-3w-0.2ti-0.25y2o3 (wt%) produced by a novel sintering technique, spark plasma sintering. it shows that our ods exhibit high density and bimodal grain size. site content the site contains brief details of current and past projects. links are provided to external websites where you can find more information on the techniques and facilities available. links are also provides to our many collaborators and partners. if you think your work should be included or linked to, please do contact me. thank you james marrow ( [email protected] ) ^ top next page: members © copyright 2009-2018 - cms made simple this site is powered by cms made simple version 2.2.8 '); }

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No such domain ac.uk


  REFERRER http://www.nominet.org.uk

  REGISTRAR Nominet UK

SERVERS

  SERVER ac.uk.whois-servers.net

  ARGS ac.uk

  PORT 43

  TYPE domain

  REGISTERED no

DOMAIN

  NAME ac.uk

NSERVER

  NS2.JA.NET 193.63.105.17

  AUTH03.NS.UU.NET 198.6.1.83

  NS3.JA.NET 193.63.106.103

  NS1.SURFNET.NL 192.87.106.101

  NS4.JA.NET 193.62.157.66

  WS-FRA1.WIN-IP.DFN.DE 193.174.75.178

  NS0.JA.NET 128.86.1.20

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