Din avgränsning ger 263 träffar.
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2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014
This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation ... participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts from...
Innehållstyp: Publikationer -
2012:02 Evaluation of activity build-up experiments
understand how the water chemistry affects the activity build-up on surfaces in different systems in Swedish nuclear power plants, which in turn provides information on conditions required to reduce the radiation ... about water chemistry conditions preferred to minimize the activity build-up. A number of experiments have previously been performed at Studsvik Nuclear AB. The effects on the activity build-up from iron, nickel...
Innehållstyp: Publikationer -
2014:09 Further Development of the Core Simulator CORE SIM: Extension to coupled capabilities for BWRs
requires a set of input data from a commercial static core simulator. The driving perturbation can be specified both as a perturbation in thermo-hydraulic parameters or directly as a perturbation in macroscopic ... distribution of the noise in coolant density, pressure, enthalpy, inlet velocity, fuel temperature and neutron flux is obtained. In this work, some results of the noise simulations, performed for the case of a homogeneous...
Innehållstyp: Publikationer -
2009:30 A Review of Evidence for Corrosion of Copper by water
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 ... corrosion may indeed be the primary canister degradation process during the utilised assessment period of 1 million years (this period is the longest time for which risk calculations will be needed according...
Innehållstyp: Publikationer -
2007:07 DECOVALEX-THMC Project - Task A
definition of the first phase, Task A-1, of the Task A of the international DECOVALEX project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting ... Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the phenomena and material properties that...
Innehållstyp: Publikationer -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
(SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N ... study in support of SSI review of the SR-Can report. The purpose is to assess the geochemical evolution of both potential buffer materials due to the intrusion of different types of groundwater, with a similar...
Innehållstyp: Publikationer -
2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment
With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can ... SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to SKB’s...
Innehållstyp: Publikationer -
2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS
Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work ... work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere barrier. For the...
Innehållstyp: Publikationer -
2011:20 A Guidebook for Evaluating Organizations in the Nuclear Industry – an example of safety culture evaluation
Organizations in the nuclear industry need to maintain an overview on their vulnerabilities and strengths with respect to safety. Systematic periodical self- assessments are necessary to achieve this overview ... regulators in carrying out organizational evaluations. Organizational evaluation process is divided into five main steps. These are: planning the evaluation framework and the practicalities of the evaluation...
Innehållstyp: Publikationer -
2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities
generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions ... restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on thorough measurements of the activity content and it must be shown that the...
Innehållstyp: Publikationer