scholarly journals Inventory of High Level Nuclear Wastes in US: Government High Level Waste, Existing Commercial High Level Waste, Existing Commercial Spent Fuel, and Projections of Commercial Spent Fuel. NRC nuclear waste management technical support in the development of nuclear waste form criteria: Task 3, Waste inventory review

1980 ◽  
Author(s):  
Debu Majumdar ◽  
Joseph Indusi
Author(s):  
Jacques Schittekat ◽  
Geert Volckaert ◽  
Michel De Valkeneer

Abstract Since mid nineties, the Belgian Government has granted funding to Belgatom and SCK•CEN to initiate collaborations with four Eastern European countries in the field of nuclear waste disposal safety. The covered matters are essentially the disposal of nuclear waste and the interim storage of spent fuel. This was a good opportunity for Belgatom and SCK•CEN to share their extensive expertise in the fields of geological disposal, site selection, performance assessment and spent fuel interim storage. In the Czech Republic, the mission deals with assistance in the bidding process for an interim dry spent fuel storage facility for fuel originating from the Dukovany site. The matters covered in the Slovak Republic are the interim storage of spent fuel and the disposal of high level waste. In Hungary, the co-operation addresses spent fuel management, low-level and high-level waste management. In Slovenia the co-operation included provision of expertise concerning LILW management and collaboration in the field of geological disposal. The co-operation is since 2001 extended to Russia, focusing on low-level waste management.


1986 ◽  
Vol 84 ◽  
Author(s):  
V. M. Oversby

AbstractPerformance assessment calculations are required for high level waste repositories for a period of 10,000 years under NRC and EPA regulations. In addition, the Siting Guidelines (IOCFR960) require a comparison of sites following site characterization and prior to final site selection to be made over a 100,000 year period. In order to perform the required calculations, a detailed knowledge of the physical and chemical processes that affect waste form performance will be needed for each site. While bounding calculations might be sufficient to show compliance with the requirements of IOCFR60 and 40CFRI91, the site comparison for 100,000 years will need to be based on expected performance under site specific conditions. The only case where detailed knowledge of waste form characteristics in the repository would not be needed would be where radionuclide travel times to the accessible environment can be shown to exceed 100,000 years. This paper will review the factors that affect the release of radionuclides from spemt fuel under repository conditions, summarize our present state of knowledge, and suggest areas where more work is needed in order to support the performance assessment calculations.


1990 ◽  
Author(s):  
K.J. Schneider ◽  
S.J. Mitchell ◽  
L.T. Lakey ◽  
A.B. Jr. Johnson ◽  
R.F. Hazelton ◽  
...  

Author(s):  
Jacques Delay ◽  
Jiri Slovak ◽  
Raymond Kowe

The Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) was launched in November 2009 to tackle the remaining research, development and demonstration (RD&D) challenges with a view to fostering the implementation of geological disposal programmes for high-level and long-lived waste in Europe. The IGD-TP’s Vision is that “by 2025, the first geological disposal facilities for spent fuel, high-level waste and other long-lived radioactive waste will be operating safely in Europe”. Aside from most of European waste management organisations, the IGD-TP now has 110 members covering most of the RD&D actors in the field of implementing geological disposal of radioactive waste in Europe. The IGD-TP Strategic Research Agenda (SRA), that defines shared RD&D priorities with an important cooperative added value, is used as a basis for the Euratom programme. It provides a vehicle to emphasise RD&D and networking activities that are important for establishing safety cases and fostering disposal implementation. As the IGD-TP brings together the national organisations which have a mandate to implement geological disposal and act as science providers, its SRA also ensures a balance between fundamental science, implementation-driven RD&D and technological demonstration. The SRA is in turn supported by a Deployment Plan (DP) for the Joint Activities to be carried out by the Technology Platform with its members and participants. The Joint Activities were derived from the individual SRA Topics and prioritized and assigned a timeline for their implementation. The deployment scheme of the activities is updated on a yearly basis.


1974 ◽  
Vol 30 (1) ◽  
pp. 28-33
Author(s):  
Gisela Dreschhoff ◽  
D. F. Saunders ◽  
E. J. Zeller

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