Visar 3269 sökträffar på ”SSM’s Scientific Council on Electromagnetic Fields”
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2025:01 Safety Concept Evaluation with Failure Tolerance Analysis
Winestedt, alla AFRY Date: Febrary 2025 Report number: 2025:01 ISSN: 2000-0456 Available at www.ssm.se SSM 2025:1 Author: Date: February 2025 Report number: 2025:01 ISSN: 2000-0456 Available at www.s ... AFRY 2025:01 SSM 2025:01 This report was commissioned by the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author(s) and do not necessarily...
Innehållstyp: Dokument -
2001:22 Work in Support of Biosphere Assessments for Solid Radioactive Waste Disposal. 2. Biosphere FEP List and Biosphere Modelling
A. Venter) 45 1 INTRODUCTION 47 1.1 BACKGROUND INFORMATION ON SFR 47 2 AMBER IMPLEMENTATION OF EXISTING MODELS 49 2.1 THE NEAR-FIELD 49 2.1.1 The Silo 51 2.1.2 Rock Vault for Intermediate Level ... methodological framework is intended to expose to scrutiny the logic of these underlying assumptions, on which the evaluation of safety performance indicators is based. Different approaches to post-closure...
Innehållstyp: Dokument -
1999:17 SSI:s ställningstaganden i slutförsvarsfrågan
TITEUTITLE: SS!s ställningstaganden i slutförvarsfråganI SS!:s Stand- points Regarding the Final Disposal of Spent Nuclear Fue! and Nuclear Waste SAMMANFATTNING: Rapporten är en sammanställning av SS!s bedöm- ... Oskarshamn - har SSI i allt högre grad kommit att efterfrågas av kommunföreträdare och allmänhet. I de s k förstudiekommunerna efterlyses SSIs stöd bl a när det gäller om metod och de kriterier för plats...
Innehållstyp: Dokument -
2017:02 Slow strain rate testing of copper in sulfide rich chloride containing deoxygenated water at 90 °C
containing deoxygenated water at 90 °C 2017:02 Authors: Richard Becker Johan Öijerholm SSM 2017:02 SSM 2017:02 SSM perspective Background Stress corrosion cracking (SCC) can occur in materials from ... conducted to a certain level of strain where after presence of cracking on the specimen surface were evaluated. Results Based on the results in this study, SCC in oxygen free copper material intended...
Innehållstyp: Dokument -
2002:22 Review of data types for the SKB site investigation programme
assessments of future impacts arising from the deep geologic disposal of spent nuclear fuel. Focus is on the types of data that make up the different elements of radiological assessment models and how the ... assessment is addressed, including the representation of the geospherebiosphere interface. Reference to SKB’s programme is made in order to determine how well the current programme will meet the needs of assessment...
Innehållstyp: Publikationer -
SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook
SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the ... Weilin Zang, Iradj Sattari-Far, Peder Andersson, Göran Sund, Lars Dahlberg and Fred Nilsson SSM English SSM has supported research work for the further development of a previously developed procedure/handbook...
Innehållstyp: Publikationer -
01:21 SKI:s utvärdering av SKB:s kompletterande redovisning till FUD-program 98. Sammanställning av remissvar
Kjell Andersson SKI Svenska...
Innehållstyp: Publikationer -
99:30 The Swedish Nuclear Power Inspectorates Evaluation of SKBs RD&D Program 98. Summary and Conclusions
SKI English...
Innehållstyp: Publikationer -
99:31 The Swedish Nuclear Power Inspectorates Evaluation of SKBs RD&D Program 98. Review Report
SKI English...
Innehållstyp: Publikationer -
2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4
accident experiments 2, 3 and 4 2014:18 Authors: Tero Manngård Ali Massih Jan-Olof Stengård SSM perspective Background Loss of Coolant Accidents (LOCA) are among the most demanding ac cidents ... in a Light Water Reactor (LWR). The lack of cooling and the drop in pressure impose large stresses on the nuclear fuel which would increase the risk of fuel rod damage and the subse quent release of...
Innehållstyp: Dokument