Pyrochemical N-waste reprocessing



Hello.

I'd like to understand what is the actual state of the art of "dry" nuclear
waste reprocessing
systems like pyroprocessing,expecially those who can deal with oxide fuel
(for example at Russian RIAR).What are their efficiency in extracting
actinides,for example U or Pu and MA in/out and their typical
decontamination factors? What their typical size/footprint ? What about
their estimated cost?

My own idea is,instead to re-burn them in fast reactors (see integral fast
reactor program) that are costly to buil and difficult to operate with
multiple recycles (I suppose due to low burn-ups achievable),to burn Pu and
minor actinides in very high burn-up (e.g. > 700 MWg/kg HM),good neutron
economy thermal reactors with only one reprocessing (pyroprocessing) cycle.I
think that pebble bed reactors developed in South Africa or generally HTGR
based could have these features
http://www.technologyreview.com/read_article.aspx?id=12727&ch=energy
http://web.mit.edu/pebble-bed/Presentation/HTGR.pdf

Finally,I found a lot of Authors are really developing this point of
view,i.e.
thermal actinides transmutation versus fast reactors.
http://aaa.nevada.edu/pdffiles/nov1104/leon.pdf
http://www3.inspi.ufl.edu/icapp04/program/abstracts/4038.pdf
http://www.physor2004.anl.gov/PHYSOR%20Program%20(FINAL).pdf (pag.50)

A big question I know,but I'd appreciate any comments,
suggestions or opinions. Thanks.













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