Hostname: page-component-cd9895bd7-7cvxr Total loading time: 0 Render date: 2024-12-29T13:05:27.193Z Has data issue: false hasContentIssue false
  • English
  • Français

Preliminary Safety Studies for Conventional Spent Fuel, MOX, and Vitrified High-Level Waste

Published online by Cambridge University Press:  10 February 2011

J.W. Schneider ,
P. Zuidema ,
P.A. Smith ,
P. Gribi ,
M. Hugi  and
M. Niemeyer
J.W. Schneider
Affiliation:
Nagra, Switzerland
P. Zuidema
Affiliation:
Nagra, Switzerland
P.A. Smith
Affiliation:
Safety Assessment Management Limited, UK
P. Gribi
Affiliation:
Colenco Power Engineering AG, Switzerland
M. Hugi
Affiliation:
Colenco Power Engineering AG, Switzerland
M. Niemeyer
Affiliation:
Colenco Power Engineering AG, Switzerland
Get access

Extract

This paper discusses the results of post-closure safety studies for two different waste streams that, according to current Swiss waste-management concepts, may be co-disposed in a single deep geological repository. The waste streams are:

• directly disposed spent UO2 and mixed-oxide (MOX) fuel

• vitrified high-level waste from the reprocessing of spent fuel

The inventories are based on a consideration of the anticipated arisings from nuclear power generation in Switzerland. A part (at least) of these arisings will be reprocessed, with the resultant vitrified high-level waste and long-lived intermediate-level waste returned to Switzerland. The Swiss electricity utilities have placed contracts with BNFL (UK) and COGEMA (France) for the reprocessing of about one third of the total arisings of spent fuel from nuclear power generation, assuming an electricity production scenario of 120 GWa(e). The decision as to whether to reprocess the remainder is currently left open, implying that up to two thirds of the arisings could be in the form of unreprocessed spent fuel for direct disposal. For the purposes of the present study, however, it is assumed that the arisings from the full 120 GWa scenario will be either directly disposed or reprocessed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 506: Symposium – Scientific Basis for Nuclear Waste Management XXI , 1997 , 1077
Copyright
Copyright © Materials Research Society 1998

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

REFERENCES

1 , Kristallin-I Safety Assessment Report, Nagra Technical Report NTB 93-22, Nagra, Wettingen, Switzerland (1994).Google Scholar
2 Vieno, T. and Nordman, H., Interim Report on Safety Assessment of Spent Fuel Disposal TILA-96, Report POSIVA-96-17, Posiva Oy, Helsinki, Finland (1996).Google Scholar