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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.
WP 2 Appendix 5 Participación Institucional De Los Municipios En El Proceso De Toma De Decisiones Para El Emplazamiento De Un Almacenamiento De Residuos Radiactivos
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).
D1-11 Prospective Case Study - Spain
D1-11 Prospective Case Study - Spain
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
WP 2 Appendix 4 Estudio Sociológico Sobre La A.M.A.C. Y El Hecho Nuclear En España
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, First Spanish National Report
The present document constitutes the First National Report of Spain, drawn up in order to meet the requirements of Article 32 of the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, adopted in Vienna on 5th September 1997. This Convention, which was signed by Spain on 30th June 1998 and ratified on 11th May 1999, entered into force on 18th June 2001.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Fourth Spanish National Report
The present document constitutes the Fourth Spanish National Report, submitted in compliance with the requirements of article 32 of the Joint Convention on Safety in the Management of Spent Fuel and Safety in the Management of Radioactive Waste, done in Vienna on September 5th 1997. This report will be examined during the review meeting of the Contracting Parties contemplated in article 30 of this Convention, which will begin in May 2012.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Second Spanish National Report
The present document constitutes the Second Spanish National Report, issued in compliance with the requirements of article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereinafter, Joint Convention), made in Vienna on September 5th 1997. This report will be examined during the Review Meeting between the Contracting Parties contemplated in article 30 of the Joint Convention, which is scheduled to start on May 15th 2006. The Ministry of Industry, Tourism and Trade (Span.
Identifying remaining socio-technical challenges at the national level: Spain
Identifying remaining socio-technical challenges at the national level: Spain
On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision.