Visar 3352 sökträffar på ”SSM’s Scientific Council on Electromagnetic Fields”
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2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios
objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential clarifications and complementary information to be supplied by SKB, and identify critical ... 2010a), hereafter referred to simply as the “Radionuclide Transport Report.” The modelling focused on two scenarios: (i) Canister Failure by Corrosion and (ii) Canister Failure by Shear Load, to evaluate...
Innehållstyp: Publikationer -
2012:08 Deterministic Assessment of Future Costs for Dismantling (FA)
study a model for advanced deterministic cost calculation has been used to nd a parametric value on the cost for dismantling of the FA-facility. The study gives good description of good practise to ... by implementation of Swedish waste management infrastructure into OMEGA database and calculation SSM 2012:08 procedures including nal disposal at Swedish repositories with up-to- date costs of disposal...
Innehållstyp: Dokument -
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...
Innehållstyp: Dokument -
2010:32 Fingerprints of zones in boreholes An approach to identify the characteristics of structures
Radiation Safety Authority, SSM. The conclusions and viewpoints present- ed in the report are those of the author/authors and do not necessarily coincide with those of the SSM. SSM Perspective This report ... dish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. Background The Swedish Nuclear...
Innehållstyp: Dokument -
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...
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 -
Appendix 1 – Radiation Protection
947 ... Simon Karlsson Date: November 2023 Report number: 2023:05e ISSN: 2000-0456 Available at www.ssm.se SSM 2023:05e Date: November 2023 Report number: 2023:05e ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten ... 4 5 1. Introduction In this appendix, the Swedish Radiation Safety Authority (SSM) presents the assumptions and approaches used in the report regarding radiation protection.
Innehållstyp: Dokument -
2004:29 Appendix F
point : 3 points on G.B. 1 point on 1, 2, 3, 4, 5, 10, 20, 50 nm from G.B. Quantification : Cliff-Lorimer method 200nm TEM result (316NG-H/33% cold work) Bright field image Dark field image Diffraction ... pattern Very small precipitate is observed in 316NG-H. TEM result (316NG-L/33% cold work) Bright field image 200nm No precipitate is observed in 316NG-L. 10 15 20 25 -20 -15 -10 -5 0 5 10 15 20...
Innehållstyp: Dokument -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
The results are compared with experimental data on cladding rupture strain, temperature and pressure. The effects of heating rate and rod internal pressure on the rupture strain are evaluated by systematic ... alloy, for which no definite constitutive relation is yet available. Tero Manngård and Ali R. Massih SSM English We present a unified model for calculation of zirconium alloy fuel cladding rupture during...
Innehållstyp: Publikationer -
2015:53 Ductile tearing – Micromechanical analyses and experimental study
experimental results in can be drawn with regard to fracture toughness and the decreasing influence on the J-integral for increasing primary load. The predictions made here also show an improvement when ... technique is a sound approach in studying the effects from residual stresses on ductile fracture at low primary loads. Tobias Bolinder SSM English In this report, the project "Ductile Tearing-Micromechanical analyses...
Innehållstyp: Publikationer