Filtered generated 65 hits.
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2005:21 DECOVALEX III PROJECT Thermal-Hydrological Modeling of the Yucca Mountain Project Drift Scale Test
Robin N. Datta with contributions from Sebastia Olivella, Claudia Gonzalez, Antonio Gens, Miguel Luna, Ronald T. Green, Scott L. Painter SKI English...
Content type: Publications -
2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents
In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...
Content type: Publications -
Forms
Content type: Publications -
2006:07 Coupled Transport/Reaction Modelling of Copper Canister Corrosion Aided by Microbial Processes
Jinsong Liu SKI English...
Content type: Publications -
2005:34 An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago
Geoff Varley, Chris Rusch SKI English...
Content type: Publications -
2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures
Background The treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific...
Content type: Publications -
Information materials
Content type: Publications -
2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository
Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...
Content type: Publications -
2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis
Background The Swedish Radiation Safety Authority (SSM) received an application for the expansion of SKB's final repository for low and intermediate level waste at Forsmark (SFR) on the 19 December 2014. SSM is tasked with the review of the application and will issue a statement to the government who will decide on the matter. An important part of the application is SKB’s assessment of...
Content type: Publications -
2015:25 Design Guide for Nuclear Civil Structures (DNB)
The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...
Content type: Publications