Hostname: page-component-586b7cd67f-2plfb Total loading time: 0 Render date: 2024-12-01T06:34:31.599Z Has data issue: false hasContentIssue false
  • English
  • Français

Treatment of Graphite Waste to Minimize Disposal Volume

Published online by Cambridge University Press:  15 February 2011

Willie C.M.H. Meyer ,
I.J. van der Walt ,
Vusi Kabila ,
Jacoba J. Badenhorst ,
Danie Moolman  and
Wouter Klopper
Willie C.M.H. Meyer
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
I.J. van der Walt
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
Vusi Kabila
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
Jacoba J. Badenhorst
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
Danie Moolman
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
Wouter Klopper
Affiliation:
South African Nuclear Energy Corporation Ltd (Necsa), P O Box 582, Pretoria 0001, South Africa
Get access

Abstract

South Africa initiated a program to significantly expand its total nuclear energy capacity by acquiring additional Pressurized Water Reactors (PWRs) and is currently researching Pebble Bed Modular Reactors (PBMRs) as next generation nuclear energy sources. The result of such an expansion in the current nuclear program will be a need for the disposal of additional nuclear waste. However, as an alternative strategy for spent PBMR fuel, the separation of the spent fuel into TRISO particles for disposal and graphite for re-use in the nuclear industry could also be considered.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1193: Scientific Basis for Nuclear Waste Management XXXIII , 2009 , 23
Copyright
Copyright © Materials Research Society 2009

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1 SEVENTH FRAMEWORK PROGRAMME EURATOM: Nuclear Research and Training Activities, CARBOWASTE: Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste, Grant Agreement No.:211333 (2008).Google Scholar
2 AREVA, Preliminary study relative to the back-end of the PBMR fuel cycle. Presentation by AREVA during a Necsa – AREVA meeting held at Necsa on March 6-7, 2007.Google Scholar
3 Bauer, Ch., “Profildesintegrations-Einrichtung fur Kugel-Brennelemente”, Kernforschungsanlage (Julich), Technisch Notiz IRW-TN-27/82, 1982.Google Scholar