Din avgränsning ger 2043 träffar.
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01:20 SKI:s yttrande över SKB:s kompletterande redovisning till FUD-program 98
261 kB...
Innehållstyp: Dokument -
2004:20 Computer Programs for Uncertainty Analysis of Solubility Calculations: Windows Version and Other Updates of the SENVAR and UNCCON Program Description and Handling Instructions (pdf 339 kB)
phases incorporating radionuclides are an essential element of estimating releases from the near-field of a final repository for spent nuclear fuel. Implementation of solubility estimates in safety assessment ... describes how the codes can be used for a case with a plutonium solubility calculation. Effects on SKI work The codes may be useful for SKI in a future evaluation of solubility calculations conducted...
Innehållstyp: Dokument -
2008:47 Selected Models for Key Processes in a Nuclear Waste Repository
Temperature field – Bentonite drying/resaturation Johan Claesson December 2007 SKI Perspective Background The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multi- ... the researchers at Chalmers University of Technology have studied the buffer, with special emphasis on the drying and saturation phases of the buffer evolution. As a complement to the detailed numerical...
Innehållstyp: Dokument -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coin- cide with those of the SSM. Background The mechanisms ... temperature influence on equilibrium conditions is rather modest, but increased temperature will nonetheless reduce the immunity area of copper under relevant groundwater conditions. SSM 2010:09 Future...
Innehållstyp: Dokument -
1999:13 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden
An SSI - EURADOS comparison exercise. Part 2: Evaluation. SUMMARY: Various mixed neutron-photon fields at workplaccs in the containment of pressurised water reactors and in the vicinity of transport ... dose eqUivalent (DE) values of the rather soft neutron fields encountered at these workplaces. The discrepancies can, however, be explained on the basis of energy dependent respon- ses of the instruments...
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 -
Country Review Report for Sweden – 7th CNS Review Meeting.pdf
182 kB ... Convention on Nuclear Safety 7th Review Meeting – 2017 International Atomic Energy Agency IAEA, Vienna Country Review Report for SWEDEN Drafted by Country ... Per INFCIRC 571, Revision 7, Para. 16-19 and Annex IV, Contracting Parties were invited to comment on the implementation of the CNS reporting guidance. Contracting Parties were also encouraged to submit...
Innehållstyp: Dokument -
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 -
2014:19 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 5, 6 and 7
loss-of-coolant accident experiments 5, 6 and 7 2014:19 Authors: Tero Manngård 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 -
2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants
1285 ... “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. SSM 2009:13e 1 Contents Summary 3 1. Premises and evaluation criteria 6 Basic principles ... preparedness 33 Nuclear safeguards 33 Emergency preparedness 33 8. Radiation protection 35 SSM 2009:13e 2 SSM 2009:13e 3 Summary The Swedish Radiation Safety Authority has through its supervision...
Innehållstyp: Dokument