Filtered generated 396 hits.
-
2010:23 On Decommissioning Costs of the Ranstad Site
A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...
Content type: Publications -
2012:28 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes
This report consists of a Technical Note in SSM’s initial review phase of SKB’s safety analysis SR-Site. The aim of the initial review of issues concerning geochemical processes in buffer and backfill in a final repository is to make a broad illustration and review of SR-Site together with its subordinate references, as well as to identify potential needs for complementary information or...
Content type: Publications -
2009:31 A Review of the Decommissioning Costs of the Ranstad Site
The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary “bench-marking” studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been...
Content type: Publications -
2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod
The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...
Content type: Publications -
SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1
SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
Content type: Publications -
2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Content type: Publications -
2008:38 Methodology for description and evaluation of cost profiles and cost structure during transitions period
A demanding task for our generation is to assure the appropriate financial resources are invested in the Swedish Nuclear Waste Fund. This will enable future generations to execute the decommissioning and dismantling of nuclear power reactors and other nuclear facilities in a prudent manner. The main aim is to fulfil the demands of environmental and health codes in a pan-European context...
Content type: Publications -
2007:26 Safety Culture Enhancement Project Final Report
At the International Conference on Safety Culture in Nuclear Installations, organized by IAEA in 2002, one concluding remark was that the regulators should encourage a sincere interest in safety culture among licensees. In line with this SKI wanted to explore a proactive path to encourage the licensees in their safety culture work. SKI also had the ambition to gain more information on the MTO...
Content type: Publications -
2007:31e Safety and Radiation Protection at Swedish Nuclear Power Plants 2006
Safety related problems in the electric systems of the Forsmark 1 reactor were the dominant event in Swedish nuclear power plants in 2006. The incident has had a significant impact on our attitude towards the reliability of how safety systems function both in Sweden and abroad. In connection with SKI’s review of the incident it was found that the company’s management system was not...
Content type: Publications -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Content type: Publications