<--- Back to Details
First PageDocument Content
Nuclear technology / Energy conversion / Radioactive waste / Graphite moderated reactors / Nuclear reprocessing / Generation IV reactor / Nuclear reactor / Sodium-cooled fast reactor / Fast-neutron reactor / Gas-cooled fast reactor / Lead-cooled fast reactor / Nuclear fuel
Date: 2016-08-12 14:26:18
Nuclear technology
Energy conversion
Radioactive waste
Graphite moderated reactors
Nuclear reprocessing
Generation IV reactor
Nuclear reactor
Sodium-cooled fast reactor
Fast-neutron reactor
Gas-cooled fast reactor
Lead-cooled fast reactor
Nuclear fuel

Microsoft PowerPoint - Future Generation Reactors_2012.pptx [Read-Only]

Add to Reading List

Source URL: www.ne.anl.gov

Download Document from Source Website

File Size: 1,58 MB

Share Document on Facebook

Similar Documents

Nuclear technology / Energy conversion / Radioactive waste / Graphite moderated reactors / Nuclear reprocessing / Generation IV reactor / Nuclear reactor / Sodium-cooled fast reactor / Fast-neutron reactor / Gas-cooled fast reactor / Lead-cooled fast reactor / Nuclear fuel

Microsoft PowerPoint - Future Generation Reactors_2012.pptx [Read-Only]

DocID: 1pdh7 - View Document

Nuclear technology / MYRRHA / SCKCEN / Generation IV reactor / Neutron / Radioactive waste / Nuclear fuel / Nuclear reactor / Actinide / Lead-cooled fast reactor / Subcritical reactor

Present status of MYRRHA and future developments Didier De Bruyn /Bong Yoo on behalf of the MYRRHA team (SCK•CEN, Mol Belgium)

DocID: 1pbTu - View Document

Nuclear reactors / Pressure vessels / Energy conversion / Nuclear technology / Light water reactors / Lead-cooled fast reactor / Generation IV reactor / Earthquake engineering / Breeder reactor / Integral fast reactor / Nuclear meltdown / Liquid metal cooled reactor

APPLICATION OF DISLOCATION DYNAMICS TO ASSESS NEUTRON IRRADIATION EFFECT ON MATERIALS WITH DIFFERENT GRAIN SIZE

DocID: 1pbmv - View Document

Piping / Mechanical engineering / Fireplaces / Tools / Plumbing / Expansion joint / Metal bellows / US Bellows / Hinged expansion joint / Joint / Lead-cooled fast reactor / Pipe

EUROPEAN COMMISSION 7th EURATOM FRAMEWORK PROGRAMMETHEME [FissionR&D activities in support of the implementation

DocID: 1oJpy - View Document

Nuclear reprocessing / Sodium-cooled fast reactor / Lead-cooled fast reactor / Generation IV reactor / Fast-neutron reactor / Reactor vessel / Nuclear fuel cycle / Coolant / Breeder reactor / Nuclear technology / Nuclear physics / Radioactive waste

GENERAL AGENDA 29 JUNE – 03 JULY 2015 JUNE 29 JULY 03 Monday, 29 June

DocID: 1fvA7 - View Document