scholarly journals Comparison of selected foreign plans and practices for spent fuel and high-level waste management

1990 ◽  
Author(s):  
K.J. Schneider ◽  
S.J. Mitchell ◽  
L.T. Lakey ◽  
A.B. Jr. Johnson ◽  
R.F. Hazelton ◽  
...  
Keyword(s):  
Waste Management ◽  
High Level Waste ◽  
Spent Fuel ◽  
High Level

The Implementing Geological Disposal Technology Platform: Key Challenges in Research and Development in Radioactive Waste Management

2014 ◽  
Author(s):  
Jacques Delay ◽  
Jiri Slovak ◽  
Raymond Kowe
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Added Value ◽  
High Level Waste ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Technology Platform ◽  
Joint Activities ◽  
The Individual ◽  
High Level

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.

scholarly journals The Implementing Geological Disposal Technology Platform – addressing the needs of new Member States

2015 ◽  
Vol 79 (6) ◽  
pp. 1591-1597 ◽  
Author(s):  
R. Kowe ◽  
J. Delay ◽  
M. Hammarström ◽  
T. Beattie ◽  
M. Palmu
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
High Level Waste ◽  
Spent Fuel ◽  
Member States ◽  
Geological Disposal ◽  
Technology Platform ◽  
Leading Role ◽  
High Level ◽  
European Union Member States

AbstractThe Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) was launched in November 2009 to facilitate international cooperation in common areas of research, development and demonstration (RD&D) with a view to advancing the implementation of geological disposal facilities for spent fuel, high-level and other 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 European waste management organisations, the IGD-TP currently has 124 members covering most of the RD&D actors in the field of implementing geological disposal of radioactive waste in Europe.Five years after its inception, the IGD-TP has been shown to play a leading role in coordinating joint actions for RD&D in radioactive waste geological disposal programmes. The work of the platform takes into account differences between the timing and challenges for the respective waste management programmes. Following implementation of Posiva's geological disposal facility in Finland it is expected that within the next 5 years the construction of the Swedish and French geological disposal facilities will commence. Within IGD-TP, the SecIGD2 project whose remit is “Coordination and Support Action under the 7th Framework programme” aims at supporting, at the European level, the networking and structuring of RD&D programmes and competences in countries with less advanced geological disposal programmes, including those in the new European Union Member States. Furthermore, the SecIGD2 supports the development and coordination of the necessary competences to meet the Vision 2025 as a part of the platform's Competence Maintenance, Education and Training (CMET) working group.

Belgian Co-Operation With the Czech Republic, Hungary, the Slovak Republic and Slovenia

2001 ◽  
Author(s):  
Jacques Schittekat ◽  
Geert Volckaert ◽  
Michel De Valkeneer
Keyword(s):  
Czech Republic ◽  
Waste Management ◽  
Nuclear Waste ◽  
Slovak Republic ◽  
High Level Waste ◽  
Spent Fuel ◽  
The Czech Republic ◽  
Geological Disposal ◽  
High Level ◽  
Interim Storage

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.

An overview of radionuclide behaviour research for the UK geological disposal programme

2012 ◽  
Vol 76 (8) ◽  
pp. 3373-3380 ◽  
Author(s):  
S. Vines ◽  
R. Beard
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Waste Disposal ◽  
High Level Waste ◽  
Spent Fuel ◽  
Geological Disposal ◽  
Nuclear Decommissioning ◽  
Disposal Facility ◽  
The Uk ◽  
High Level

AbstractIn the UK, radioactive wastes currently planned for disposal in a geological disposal facility (GDF) are intermediate-level waste, some low-level waste and high-level waste. Disposal of other materials, including spent fuel, separated uranium and separated plutonium are also included in the planning of a GDF, if such materials are classified as wastes in the future. This paper gives an overview of the radionuclide behaviour research studies of the Nuclear Decommissioning Authority Radioactive Waste Management Directorate (NDA RWMD). The NDA RWMD's current understanding of the processes that control radionuclide behaviour in groundwater and how the engineered and natural barriers in a GDF would contain radionuclides is presented. Areas requiring further work are also identified.

TRU Recycling Options for Environmentally Friendly and Proliferation-Resistant Nuclear Fuel Cycle of FBR

2010 ◽  
Author(s):  
Sidik Permana ◽  
Mitsutoshi Suzuki
Keyword(s):  
High Performance ◽  
Fuel Cycle ◽  
Operation Time ◽  
Nuclear Nonproliferation ◽  
High Level Waste ◽  
Minor Actinide ◽  
Spent Fuel ◽  
Closed Fuel Cycle ◽  
The Core ◽  
High Level

The embodied challenges for introducing closed fuel cycle are utilizing advanced fuel reprocessing and fabrication facilities as well as nuclear nonproliferation aspect. Optimization target of advanced reactor design should be maintained properly to obtain high performance of safety, fuel breeding and reducing some long-lived and high level radioactivity of spent fuel by closed fuel cycle options. In this paper, the contribution of loading trans-uranium to the core performance, fuel production, and reduction of minor actinide in high level waste (HLW) have been investigated during reactor operation of large fast breeder reactor (FBR). Excess reactivity can be reduced by loading some minor actinide in the core which affect to the increase of fuel breeding capability, however, some small reduction values of breeding capability are obtained when minor actinides are loaded in the blanket regions. As a total composition, MA compositions are reduced by increasing operation time. Relatively smaller reduction value was obtained at end of operation by blanket regions (9%) than core regions (15%). In addition, adopting closed cycle of MA obtains better intrinsic aspect of nuclear nonproliferation based on the increase of even mass plutonium in the isotopic plutonium composition.

scholarly journals Survey of waste package designs for disposal of high-level waste/spent fuel in selected foreign countries

1989 ◽  
Author(s):  
K.J. Schneider ◽  
L.T. Lakey ◽  
D.J. Silviera
Keyword(s):  
High Level Waste ◽  
Spent Fuel ◽  
Waste Package ◽  
Foreign Countries ◽  
High Level

scholarly journals Spent Fuel as a Waste Form - Data Needs to Allow Long Term Performance Assessment Under Repository Disposal Conditions.

1986 ◽  
Vol 84 ◽  
Author(s):  
V. M. Oversby
Keyword(s):  
Performance Assessment ◽  
Waste Form ◽  
High Level Waste ◽  
Detailed Knowledge ◽  
Spent Fuel ◽  
Expected Performance ◽  
High Level ◽  
Term Performance ◽  
Physical And Chemical ◽  
Waste Repositories

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.

Assessment of Redox Conditions in the Near Field of Nuclear Waste Repositories: Application to the Swiss high-level and intermediate level waste disposal concept

2003 ◽  
Vol 807 ◽  
Author(s):  
Paul Wersin ◽  
Lawrence H. Johnson ◽  
Bernhard Schwyn
Keyword(s):  
Solid Phase ◽  
Near Field ◽  
Intermediate Level ◽  
Redox Conditions ◽  
High Level Waste ◽  
Redox Potentials ◽  
Spent Fuel ◽  
Reducing Conditions ◽  
High Level ◽  
Waste Repositories

ABSTRACTRedox conditions were assessed for a spent fuel and high-level waste (SF/HLW) and an intermediate-level waste (ILW) repository. For both cases our analysis indicates permanently reducing conditions after a relatively short oxic period. The canister-bentonite near field in the HLW case displays a high redox buffering capacity because of expected high activity of dissolved and surface-bound Fe(II). This is contrary to the cementitious near field in the ILW case where concentrations of dissolved reduced species are low and redox reactions occur primarily via solid phase transformation processes.For the bentonite-canister near field, redox potentials of about -100 to -300 mV (SHE) are estimated, which is supported by recent kinetic data on U, Tc and Se interaction with reduced iron systems. For the cementitious near field, redox potentials of about -200 to -800 mV are estimated, which reflects the large uncertainties related to this alkaline environment.

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