Hostname: page-component-669899f699-8p65j Total loading time: 0 Render date: 2025-04-25T13:07:55.581Z Has data issue: false hasContentIssue false
  • English
  • Français

Repository performance assessment and advanced fuel cycle models for input to decision making of options for nuclear waste and resource management

Published online by Cambridge University Press:  21 March 2011

J.S. Small ,
C.H. Zimmerman ,
D.R. Parker ,
C. Robbins ,
A.E. Bond  and
G.A. Stevens
J.S. Small
Affiliation:
Nexia Solutions Ltd., Warrington, UK
C.H. Zimmerman
Affiliation:
Nexia Solutions Ltd., Sellafield, UK
D.R. Parker
Affiliation:
Nexia Solutions Ltd., Sellafield, UK
C. Robbins
Affiliation:
Grallator Modelling, Simulation, & Software, Derbyshire, UK
A.E. Bond
Affiliation:
Nexia Solutions Ltd., Warrington, UK
G.A. Stevens
Affiliation:
Nexia Solutions Ltd., Warrington, UK
Get access

Abstract

A methodology and computer software is described which can be used to track the inventory of radionuclides as they are affected by various nuclear, physical and chemical processes during reactor, storage, effluent and disposal phases of the nuclear fuel cycle. Such a model is required to provide an assessment of economic, environmental and societal performance indicators which underpin decisions regarding options for the use and management and nuclear materials. An example generic deep repository model is described which can be used to provide an indicator of environmental performance of vitrified high level waste and UO2 and mixed oxide (MOX) spent fuels. The assessment models highlight the significance of the I-129 fission product which necessitates the use of appropriate dose assessment models to be considered for each process step of the nuclear fuel cycle in order that a complete environmental assessment of process options can be determined.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 102.1
Copyright
Copyright © Materials Research Society 2006

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.)

Article purchase

Temporarily unavailable

References

REFERENCES

1. Robbins, C., Parker, D. R. and Zimmerman, C. H. (2003) “Limits, Timescales and Optimisation of Fast Neutron Reactor P&T Schemes”, Proceedings of Global 2003, New Orleans, LA, pp 1011–1018.Google Scholar
2. ICRP 68 (1994) Dose coefficients for intakes of radionuclide by workers. Annals of the ICRP, 24, ICRP Publication 68.Google Scholar
3. SKB (1999). Deep repository for spent nuclear fuel SR 97 – Post closure safety. SKB Technical report TR-99-06. Swedish Nuclear Fuel and Waste Management Co. Stockholm.Google Scholar
4. Lindgren, M. and Lindstrom, F. (1999). SR 97 – Radionuclide transport calculations. SKB Technical report TR-99-23. Swedish Nuclear Fuel and Waste Management Co. Stockholm.Google Scholar
5. NAGRA (2002) Project Opalinus Clay Safety Report. Nagra Technical Report NTB 02-05.Google Scholar
6. QuantiSci and Quintessa (2002). AMBER 4.4 Reference Guide. QuantiSci Report, Version 1.0, QuantiSci Limited, Culham, Oxon.Google Scholar
7. Enviros (2003) AMBER Users and references version 1.02e Enviros Scientific Consulting.Google Scholar
8. Andersson, J (1999). SR 97 Data and Data Uncertainties. Compilation of Data and Data Uncertainties for Radionuclide Transport Calculations. SKB Technical Report TR-99-09, Swedish Nuclear Fuel and Waste Management Company, Stockholm.Google Scholar
9. Oversby, V.M. (1999). Uranium dioxide, SIMFUEL, and spent fuel dissolution rates – a review of published data. SKB Technical report TR-99-22. Swedish Nuclear Fuel and Waste Management Co. Stockholm.Google Scholar