Category of Content
Siting Experience Documents Only
Publication Date
Country
Keywords
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 10 Balance of Power: Principles and Good Practices for Local Stakeholders to Influence National Decision-making Processes
WP 2 Appendix 10 Balance of Power: Principles and Good Practices for Local Stakeholders to Influence National Decision-making Processes
Our basic position is that the outcomes of policy-making in radioactive waste management (RWM) should be driven by the will of the people through democratic processes. Achieving this inclusiveness requires good practices to increase local influence on what is essentially a national policy process. However inclusiveness poses significant practical problems; can society afford lengthy and costly consultation processes, often perceived as inefficient and ineffective?
WP 3 Quality of decision-making process Proposed Framework for Decision-making Processes
WP 3 Quality of decision-making process Proposed Framework for Decision-making Processes
The long-term governance of radioactive waste is complex socio-technical issue. The disposition of radioactive waste is decided on ethical grounds, having to take into account a variety of other dimensions (society, economy, ecology, politics, time, space, and technology). Thereto, a study of variants is required. Decision theory, in principle, takes diverse options as a starting point begin as the basis of a decision.
WP 2 Appendix 9 Principles and Good Practices for Local Actors to Influence National Decision-Making Processes
WP 2 Appendix 9 Principles and Good Practices for Local Actors to Influence National Decision-Making Processes
The outcomes of policy-making in radioactive waste management (RWM) should be driven by the will of the people through democratic processes. Achieving this inclusiveness requires good practices to increase local influence on what is essentially a national policy process. However inclusiveness poses significant practical problems; can society afford lengthy and costly consultation processes, often perceived as inefficient and ineffective?
WP 2 Appendix 7 Influence of Local Communities on Decision Processes: Experience of Copeland and Shetland Islands
WP 2 Appendix 7 Influence of Local Communities on Decision Processes: Experience of Copeland and Shetland Islands
The focus of this case study is the concerns of two communities affected, albeit in different ways, by radioactive waste management and the decommissioning of nuclear installations. These are communities affected by the decisions of nuclear operators, regulators and national policy makers. As such they interact with these organisations and quite naturally they are concerned about their long-term sustainability.