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Dissolved Concentration Limits of Elements with Radioactive Isotopes
Dissolved Concentration Limits of Elements with Radioactive Isotopes
The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.
EBS Radionuclide Transport Abstraction
EBS Radionuclide Transport Abstraction
The purpose of this report is to develop and analyze the Engineered Barrier System (EBS) Radionuclide Transport Abstraction Model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment: Engineered Barrier System: Radionuclide Transport Abstraction Model Report (BSC 2006 [DIRS 177739]). The EBS Radionuclide Transport Abstraction (or RTA) is the conceptual model used in the Total System Performance Assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ).
Waste Package Flooding Probability Evaluation
Waste Package Flooding Probability Evaluation
The objective of this calculation is to evaluate the probability of flooding a waste package with seepage water. Disruptive events can affect the Engineered Barrier System (EBS) components and have the potential to allow an advective flow of seepage water to reach the waste package. The advective and diffusive flow paths into the waste package have the potential to result in water accumulation inside the waste package, which in turn can lead to a potentially critical configuration. This calculation will evaluate the following:
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.
In-Drift Precipitates/Salts Model
In-Drift Precipitates/Salts Model
This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).
Engineered Barrier System: Physical and Chemical Environment
Engineered Barrier System: Physical and Chemical Environment
The purpose of this model report is to describe the evolution of the physical and chemical environmental conditions within the waste emplacement drifts of the repository, including the drip shield and waste package surfaces. This report documents the development of a new process-level model, the near-field chemistry (NFC) model, and develops two abstraction models.
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.