Filtered generated 399 hits.
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2014:39 Technical Note, “Wormhole” and Multiple Loss of Buffer Safety Function Scenarios
This Technical Notes reviewed the issues that may cause canister corrosion other than the cases evaluated by SKB, which may belong to “What-if” canister corrosion scenarios. This Notes, in particular, addressed two potential canister corrosion scenarios: “wormhole” formation and loss of multiple buffer safety functions. The “wormhole” scenario was hypothesized during the SSM Workshop on...
Content type: Publications -
2015:05 Technical Note, Review of uncertainty propagation and sensitivity analysis in SR-Site Main Review Phase
The review assignment SSM2014-2060 “Review of uncertainty and sensi- tivity analysis in SR-Site” addressed three issues: 1. Adequacy of the methods adopted by SKB for conducting sensitivity analyses 2. Approach for use of conservative and best-estimate parameter values 3. Propagation of uncertainty for the corrosion scenario Adequacy of the methods for sensitivity analyses: The sensitivity...
Content type: Publications -
2015:01 Technical Note, Rock Mechanics - Thermal properties and thermal modelling of the rock in a repository of spent nuclear fuel at Forsmark – Main Review Phase
In preparation for the review of SKB's license application for a disposal of spent nuclear fuel, SSM has conducted a series of modelling studies related to the design, construction and long-term safety of a repository at Forsmark. Several of the presented modelling works are related to the thermal evolution of the repository with time. This report extracts the results from independent SSM...
Content type: Publications -
2009:30 A Review of Evidence for Corrosion of Copper by water
The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...
Content type: Publications -
2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
SKI is preparing to review the license applications being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB) for a final repository for the geological disposal of spent nuclear fuel (SFL-2) in the year 2009. As part of its preparation, SKI is conducting a series of technical workshops on key aspects of the Engineered Barrier System (EBS) and spent fuel. This workshop...
Content type: Publications -
2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code
The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...
Content type: Publications -
2007:08 DECOVALEX-THMC - Task B
This report summarizes the work contributed to Phase 2 of Task B of the international DECOVALEX-THMC project, which took place during the period of March 2004 to May 2006. The Phase 2 work incorporated the use of a wide range of numerical models to simulate the failure of a number of intact rock core samples, from the APSE tunnel at Äspö HRL, as tested in uniaxial compression and other...
Content type: Publications -
2009:32 On Younger Stakeholders and Decommissioning of Nuclear Facilities
An appropriate balance in this regard must be based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data...
Content type: Publications -
2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study
Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...
Content type: Publications -
2019:09 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Decommissioning of the nuclear reactor Ågesta in Sweden.
Content type: Publications