Showing 3314 hits for ””
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2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock
SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...
Content type: Publications -
2021:06 Quality Assurance Review of the Swedish Nuclear Fuel and Waste Management Company’s LOT Experiment (Phase S2 and A3) at the Äspö Facility in Sweden
SSM perspective Background This report presents a quality assurance (QA) review of the work done by SKB to retrieve the S2 and A3 parcels from the Long term test of buffer material (the LOT experiment) at the Äspö Hard Rock Laboratory. Each LOT parcel comprises a heated copper tube surrounded by bentonite, with a number of copper coupons and various other test and monitoring instruments...
Content type: Publications -
2023:10 General data in accordance with the requirements in Article 37 of the Euratom Treaty
Oskarshamn Very Low-level Radioactive Waste Disposal Facility, MLA3, Sweden...
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Shipment of sealed sources between the member states of the European Community
Standard document to be used pursuant to Council Regulation (EEC) No 1493/93. You need Adobe Acrobat Reader in order to read and fill out PDF forms. SSM Svenska Standard document to be used pursuant to Council Regulation (EEC) No 1493/93. You need Adobe Acrobat Reader in order to read and fill out PDF forms.
Content type: Publications -
Health declaration – Work involving ionising radiation
You need Adobe Acrobat Reader in order to read and fill out PDF forms. SSM Svenska You need Adobe Acrobat Reader in order to read and fill out PDF forms.
Content type: Publications -
In case of an alarm from Ringhals nuclear power plant – What you need to know
SSM English...
Content type: Publications -
2020:12 Assessment of the QT-COOL coolant channel module against the PBF RIA 1-2 experiment
SSM perspective Background The fuel rod analysis program SCANAIR has been developed by IRSN (Institut de Radioprotection et de Sûreté Nucléaire) for analysis of reactivity initiated accidents (RIA) in light water reactors. The Swedish Radiation Safety Authority (SSM) has access to SCANAIR in exchange for annual contributions for its further development. This ensures a possibility...
Content type: Publications -
2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents
In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors. The objective is to assess if the inertia effects are important enough to warrant modification of QT-COOL, a coolant channel module for two-phase flow that has recently been implemented as...
Content type: Publications -
2019:17 ENSREG 1st Topical Peer Review – Ageing Management, Swedish National Action Plan
SSM perspective Background The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The member states, acting through the European Nuclear Safety Regulators Group (ENSREG), have decided that the topic for the first topical peer review is ageing management. This report...
Content type: Publications -
02:21 (SSI 2002:12) Formulation and Presentation of Risk Assessments to Address Risk Targets for Radioactive Waste Disposal
R. D. Wilmot SKI English...
Content type: Publications