The role of conceptual models in demonstrating repository post-closure safety

The role of conceptual models in demonstrating repository post-closure safety Download PDF EPUB FB2

Role of conceptual models in demonstrating repository post-closure safety. Paris: Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; [Washington, D.C.: OECD Publications and Information Centre, distributor], © (OCoLC) Material Type. • Demonstrate that long-term safety from the hazards presented by SNF can be evalu-ated for a deep horizontal drillhole repository sited in a sedimentary host formation, using established simulation tools and analysis methods.

• Provide arguments in support of a generic post-closure safety. For a repository, the safety case may relate to a given stage of development. In such cases, the expected to evolve through the timescale of the operational and post-closure safety assessments.

Lecture - Introduction to Safety Assessment and Safety Case 27 use of alternative conceptual models to demonstrate. of a repository to provide such long-term safety.

Addressing the post-closure phase is a particular challenge due to its long timescale (i.e. of the order of hundreds of thousands of years), which raises subsequent issues of how to demonstrate safe performance of the repository with adequate confidence based on present analyses and data.

Role and Examples. YMAndrews-Van Luik_NWTRB_ppt is to demonstrate post-closure regulatory compliance uncertain values for performance parameters establish a conceptual model of the repository system and a trajectory of expected repository performance that is reasonably predictable and can be.

The Safety Analysis Report addressed repository safety before and after permanent closure, research and development programs to resolve safety questions, the performance confirmation program, and management systems. Acceptance of the license application for review by the Nuclear Regulatory Commission staff without requests for additional.

including concrete degradation in the repository environment. For this purpose, the characterisation and evaluation of the long-term behaviour of cementitious materials, the development of silo closure options, and safety re-assessments concerning concrete degradation in the repository environment have been carried out in this IAEA-CRP.

As a methodology demonstration for the Office of Nuclear Waste Isolation (ONWI), the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program conducted an initial reference site analysis of the long-term effectiveness of a salt dome repository.

for assessing the post-closure safety of nuclear waste storage in geologic. • The first part (safety of the disposal concept) concerned the demonstration of long-term safety of the multi-barrier system under the condition that the assumed host-rock properties used for safety assessment are representative for a volume of rock large enough to host the repository.

This part was assessed positively by HSK. Post-closure monitoring goals also include 2, 4, 5, 6, and 7 above. A widely accepted objective of the international community is that long-term safety of the repository must not rely on institutional controls (i.e., monitoring of the repository) after it has been sealed and closed (IAEA, ).

Management of Uncertainty in Safety Case: The Role of Risk Stockholm, Sweden FebruaryPresentation Out I i ne 0 0 0 0 conceptual models - Incorporate insights gained through post-closure.

The post-closure performance of a generic horizontal drillhole repository for the disposal of spent nuclear fuel (SNF) is quantitatively evaluated using a physics-based numerical model that accounts for coupled thermal-hydrological flow and radionuclide transport processes.

The model incorporates most subcomponents of the repository system, from individual waste canisters to the geological far. •Severe Shaft Seal Failure Scenario – Conceptual model is the same as for the Normal Evolution Scenario – starts with degraded concrete seals – Severe Failure Scenario uses more pessimistic parameter values Significantly degraded physical and chemical characteristics of the concrete monoliths and shaft seals Increased permeability of the repository/shaft EDZs (EDZ.

Radioactive Waste Repository Development, Safety Assessment, and Site Characterization The conceptual model for radionuclide “Post-Closure Safety. • Digital models have been common in engineering since the late s but today’s focus on Model-based Engineering goes beyond the use of disparate models • Model-based Engineering moves the record of authority from documents to digital models including M-CAD, E-CAD, SysML and UML managed in a data rich environment • Shifting to model-based.

[Show full abstract] conceptual model to describe enterprises from a holistic perspective. The proposed model is based on relationships between the ArchiMate language and bodies of knowledge (BOKs). conceptual models of the Yucca Mountain site and the performance of the repository.

Such considerations were needed to assure that site investigations would gather data to confirm or rule-out alternative conceptual models, in addition to gathering data to confirm the preferred concept. Other NRC staff comments on the CDSCP concerned: (1) the. benefited from the development of conceptual models for comparative research.

' Two sets of studies on comparative environmental policy have partially adopted central principles from comparative politics theory. One group has used the concept of economic development to explain differences in environmental policy.

accomplished by reviewing the fundamental concepts behind safety assessment and demonstrating how waste package models can be used to support safety assessment. Safety assessment for low- and intermediate-level wastes is a complicated process involving assumptions about the appropriate conceptual model to use and the data required to support these.

consider alternative models of features and processes that are consistent with the available data and scientific understanding and evaluate the effects of the alternative conceptual models on performance of the repository; 5.

provide a technical basis for either inclusion or exclusion of specific FEPs in the performance assessment; and. The QSS model has been developed to understand the study of hypothetical post-closure criticality events in a GDF. The model has been successfully applied to simulate the Oklo zone 2 natural reactor and the results of the calculation are in good agreement .ty (UCF) would be constructed and site-specific research and technology demonstration would be performed.

During this period, in-situ characteristics of the site at repository depth would be obtained and the final design and safety assessments would be prepared prior to final construc-tion and operation of the repository.

Project leader, Knowledge Repository. Dr. Joseph conceived the idea and on patients, staff and families, developing conceptual models demonstrating relationships identified through the review and developing key point developing a book compiling multiple resources – literature review, best.