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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.
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, written questions submitted to Luxembourg
Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2009
Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2009
Luxembourg has signed the Joint Convention on 1st October 1997 and is a Party thereof since 19 November 2001. The Convention entered into force on 21 June 2001. Luxembourg has no nuclear power plant, no other fuel-cycle facility, no research reactor and no other facility generating radioactive substances. Thus many requirements of the Joint Convention do not apply to Luxembourg. It further has no spent nuclear fuel and no high level radioactive waste on its territory.
Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2006
Luxembourg, National Report on the measures taken by Luxembourg to fulfill the obligations laid down in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 2006
Luxembourg has signed the Joint Convention on 1st October 1997 and is a Party thereof since 19 November 2001. The Convention entered into force on 21 June 2001. Luxembourg has no nuclear power plant, no other fuel-cycle facility, no research reactor and no other facility generating radioactive substances. Thus many requirements of the Joint Convention do not apply to Luxembourg. It further has no spent nuclear fuel and no high level radioactive waste on its territory.
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg