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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.
Guidance on the Selection of PTA Tools: For Stakeholders involved in Radioactive Waste Governance WP1
Guidance on the Selection of PTA Tools: For Stakeholders involved in Radioactive Waste Governance WP1
This research on "e;Guidance on the selection of PTA tools for stakeholders involved in radioactive waste governance"e; was performed under the umbrella of COWAM2-'Work Package 1' (WP1). Through a dialogue on enhancing involvement at a local level, WP1 allows local stakeholders to examine the issues they face in building a democratic local governance process. WP1 also tests how Participatory Technology Assessment (PTA) methods can offer a consensual framework and a platform for deliberative co-decision among scientific and societal actors at the local level.
Tools for Local Stakeholders in Radioactive Waste Governance: Challenges and Benefits of Selected PTA Techniques WP1
Tools for Local Stakeholders in Radioactive Waste Governance: Challenges and Benefits of Selected PTA Techniques WP1
The investigation consists of three parts and shall provide an input to the – empirical – PTA-2 study to be undertaken by SCK•CEN (called “lens”):<br>A. Compilation of – selected – existing PTA methods and procedures identifying requisites, practices, benefits, and challenges to answer the key questions in the context of WP1 about a PTA “toolbox”: “What can you apply, when can you apply, and what is needed to apply?” The multi-dimensional context of a possible “PTA situation” is analysed; suitable and nonsuitable methods, techniques and procedures are discussed.<br>B.
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
During the 1990s, nuclear waste programmes in nearly every concerned country met many difficulties. Nuclear waste management was seen as a technical issue, and the local communities were only involved in the last stage of the decision-making process when almost all components of the decision were already fixed. The management of high level radioactive waste is now recognised as a complex decision-making process entailing technical, ethical, social, political and economic dimensions where no solution can be reached solely on the basis of technical considerations.