Visar 3308 sökträffar på ”SSM’s Scientific Council on Electromagnetic Fields”
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00:39 SKI:s och SSI: gemensamma granskning av SKB:s Säkerhetsrapport 97. Granskningsrapport
311 kB...
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02:09 SKI:s yttrande över SKB:s redovisning av FUD-program 2001 (pdf 1,66 Mb)
använt kärnbränsle och kärnavfall (prop. 1980/81:90, bilaga 1, s. 319, prop. 1983/84:60, s. 38, prop. 1997/98:145, s. 381, prop. 1992/93:98, s. 29 samt näringsutskottets betänkanden 1988/89:NU31 och 1989/90:NU24): ... fylla något egentligt syfte att ytter- ligare reglera denna fråga i kärntekniklagen (prop. 1997/98:145, s. 381 fjärde stycket). 2.6 Systemanalys Remissinstansernas synpunkter Kungliga tekniska högskolan...
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01:20 SKI:s yttrande över SKB:s kompletterande redovisning till FUD-program 98
261 kB...
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2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
fracture mechanics code PRO-LOCA 2016:37 Author: Andrey Shipsha SSM 2016:37 SSM 2016:37 SSM perspective Background SSM and the Swedish nuclear power plant owners have financed Inspecta Technology ... to PWSCC degradation, and a BWR pipe under fatigue cracking. 3. The main influencing parameters on the predicted probabilities for the PWSCC case are growth rate, weld residual stress, inspection...
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00:29 User Guide to SUNDT A Simulation Tool for Ultrasonic NDT
demands on reliability of used procedures and methods applied in e.g. nuclear and pressure vessel industries have enforced this fact. To qualify the procedures, extensive experimental work on test blocks ... ......................................................9 4.3 Specifying the parameters of the Probe(s)....................................................................13 4.4 Selection of Defect.....
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Appendix 3 The nuclear power plants
3785 kB ... Karlsson Patrick Isaksson Jonas Lindgren Elisabeth Tengborn Anna Maria Blixt Buhr Ulf Bäverstam SSM 2017:27e 2017:27e Authors: Date: May 2019 Report number: 2017:27e ISSN: 2000-0456 Available at ... Karlsson Patrick Isaksson Jonas Lindgren Elisabeth Tengborn Anna Maria Blixt Buhr Ulf Bäverstam SSM 2017:27e 3 Contents 1. Summary ..........................................................
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2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik
Lindskog January 2007 SKI perspective Background The nuclear power utilities must under the Act on the Financing of the Management of Certain Radioactive Waste etc. (1988:1597), sometimes referred ... exposures, duration times, amounts of waste, manpower, personnel and equipment needed Nevertheless, SKI ´s standpoint is that all measures that enhance the overall quality of the calculation of fees to the...
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2019:09 General data in accordance with theequirements in Article 37 of the Euratom Treaty, Decommissioning of the nuclear reactor Ågesta in Sweden
of the Euratom Treaty Decommissioning of the nuclear reactor Ågesta in Sweden. 2019:09 SSM 2019:09 SSM 2019:09 Abstract The purpose of this report is to provide the European Commission with general ... follows the recommendations given in 2010/635/Euratom on the application of Article 37 of the Euratom Treaty. The Ågesta reactor was Sweden´s rst commercial reactor. The reac- tor is a pressurized...
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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...
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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