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Probabilistic External Criticality Evaluation (SCPB: N/A)
Probabilistic External Criticality Evaluation (SCPB: N/A)
This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.
Geochemistry Model Validation Report: External Accumulation Model
Geochemistry Model Validation Report: External Accumulation Model
The purpose of this report is to document and validate the external accumulation model that predicts accumulation of fissile materials in the invert, fractures and lithophysae in the rock beneath a degrading waste package containing spent nuclear fuel (SNF) in the monitored geologic repository at Yucca Mountain. (Lithophysae are hollow, bubblelike structures in the rock composed of concentric shells of finely crystalline alkali feldspar, quartz, and other materials (Bates and Jackson 1984 [DIRS 128109], p.
EQ6 Calculations for Chemical Degradation of Pu-Ceramic Waste Packages
EQ6 Calculations for Chemical Degradation of Pu-Ceramic Waste Packages
In this study, the long-term geochemical behavior of waste package (WP), containing Pu-ceramic, was modeled. The ceramic under consideration contains Ti, U, Pu, Gd and Hf in a pyrochlore structure; the Gd and Hf stabilize the mineral structure, but are also intended to provide criticality control. The specific study objectives were to determine:
1) the extent to which criticality control material, suggested for this WP design, will remain in the WP after corrosion/dissolution of the initial package configuration (such that it can be effective in preventing criticality), and
Analysis of Critical Benchmark Experiments for Configurations External to WP
Analysis of Critical Benchmark Experiments for Configurations External to WP
The Disposal Criticality Analysis Methodology Topical Report (Reference 1) states that the accuracy of the criticality analysis methodology (MCNP Monte Carlo code and cross-section data) designated to assess the potential for criticality of various configurations in the Yucca Mountain proposed repository is established by evaluating appropriately selected benchmark critical experiments.
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
Preliminary Criticality Analysis of Degraded SNF Accumulations External to a Waste Package (SCPB: N/A)
This study is prepared by the Mined Geologic Disposal System (MODS) Waste Package Development Department (WPDD) to provide input to a separate evaluation on the probablility of criticality in the far- field environment. These calculations are performed in sufficient detail to provide conservatively bounding configurations to support separate probabilistic analyses.
Report On External Criticality of Plutonium Waste Forms In A Geologic Repository
Report On External Criticality of Plutonium Waste Forms In A Geologic Repository
This report presents the analyses and results for the potential occurrence of external criticality events which could result from plutonium waste forms emplaced in a geologic repository similar to the one being developed at Yucca Mountain. The analyses evaluate both the MOX spent fuel and the immobilized plutonium waste forms in a repository if the waste package has degraded and if the fissile material has migrated to the invert and out into the far-field.
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
Aspects of Governance in the Practical Implementation of the Concept of Reversibility for Deep Geological Disposal
The European project COWAM in Practice (CIP) was aimed to lead for three years (2007-2009) a process of monitoring, analyzing and evaluating the governance linked with radioactive waste management. This project, in cooperation with a research group and stakeholders, was conducted in parallel in 5 European countries (Spain, France, United Kingdom, Romania, Slovenia).
D1-10 Prospective Case Study - Slovenia
D1-10 Prospective Case Study - Slovenia
Identifying remaining socio-technical challenges at the national level: Slovenia
Identifying remaining socio-technical challenges at the national level: Slovenia
The use of nuclear energy has a strong tradition in Slovenia. In 1949 the Institute Josef Stefan was founded, devoted to research in physics, with great emphasis on nuclear physics. A few years later (1966) the research nuclear reactor TRIGA started to work in the vicinity of capital city Ljubljana, to support its research.
First Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
First Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The National Report on Fulfilment of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management is prepared in fulfilment of Slovenia’s obligation as a Contracting Party to this Convention.
This report was prepared by the Slovenian Nuclear Safety Administration. Contributions to the report were made by the Krško NPP, the Jožef Stefan Institute, the Agency for Radwaste Management, the Žirovski Vrh Uranium Mine and the Slovenian Radiation Protection Administration.
Second Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Second Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The National Report on Fulfilment of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management is prepared in ful- filment of Slovenia‘s obligation as a Contracting Party to this Convention.
Third Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Third Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The National Report on Fulfilment of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management is prepared in fulfilment of Slovenia's obligation as a Contracting Party to this Convention.
Second Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Answers to questions raised by other contracting parties
Second Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Answers to questions raised by other contracting parties
Answers to questions raised by other contracting parties under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management were prepared by the Slovenian Nuclear Safety Administration, the Kr_ko NPP, the Agency for Radwaste Management and the Ministry of Infrastructure and Spatial Planning.
Fourth Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Fourth Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The National Report on Fulfilment of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management is prepared in fulfilment of Slovenia's obligation as a Contracting Party to this Convention.
Third Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Answers to questions raised by other contracting parties
Third Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Answers to questions raised by other contracting parties
Answers to questions raised by other contracting parties under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management were prepared by the Slovenian Nuclear Safety Administration, the Kr_ko NPP, the Agency for Radwaste Management and the Ministry of Infrastructure and Spatial Planning.
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
In 2010, there were no events that posed a serious radiological threat to the population in Slovenia. There were also no particularities in relation to the services of radiation practices and operators of radiation facilities.
The Krško NPP operated without shutdowns and production was interrupted only for the annual outage. In 2010, the power plant produced 5.7 TWh in total and achieved 89.9% availability. The nuclear power plant had no major problems during the September floods, when the Sava river otherwise seriously threatened settlements in Posavje.