Filtered generated 761 hits.
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2005:16 Radon Risk Map of Estonia; Explanatory text to the Radon Risk Map Set of Estonia at the scale of 1:500,000
Radon Risk Map of Estonia has been produced to provide an overview of the concentration of the radioactive inert gas radon-222 in soil air and of the concentrations of uranium, thorium and potassium in the soil. The aim of the map is to serve as a tool in the effort to reduce the health risk posed by radon in dwellings and workplaces. The Radon Risk Map gives general information on areas...
Content type: Publications -
2009:02 Screening calculations for radioactive waste releases from non-nuclear facilities
A series of screening calculations have been performed to assess the potential radiological consequences of discharges of radioactive substances to the environment arising from waste from non-nuclear practices. Solid waste, as well as liquids that are not poured to the sewer, are incinerated and ashes from incineration and sludge from waste water treatment plants are disposed or reused at...
Content type: Publications -
2009:01 Decommissioning of the Nuclear Reactors R2 and R2-0 at Studsvik, Sweden – General Data as called for under Article 37 of the Euratom Treaty
The report describes the plans for decommissioning of the nuclear research and material test reactors R2 and R2-0, situated at the Studsvik site in Sweden. The purpose of the document is to serve as information for the European Commission, and to fulfil the requirements of Article 37 of the Euratom Treaty. According to Article 37, each Member State shall provide the Commission with such...
Content type: Publications -
2005:20 Expert Panel Elicitation of Seismicity Following Glaciation in Sweden
The Swedish Radiation Protection Authority, the Swedish Nuclear Power Inspectorate and the Swedish Nuclear Fuel and Waste Management Company have jointly carried out a project on expert panel elicitation on the issue of glacial induced Swedish earthquakes. Following a broad nomination procedure, 5 experts were chosen by a selection committee of 4 professors within Earth sciences disciplines.
Content type: Publications -
2007:02e Radiation Environment in Sweden, summary
The radiation environment to which the population of Sweden is exposed is dominated by medical investigations and background radiation from the ground and building materials in our houses. That is the conclusion of the first general Swedish summary of environmental monitoring data and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of...
Content type: Publications -
1999:13 Determination of the Neutron and Photon Dose Equivalent at Work Places in Nuclear Facilities of Sweden
Various mixed neutron-photon fields at workplaccs in the containment of pressurised water reactors and in the vicinity of transport containers with spent fuel elements were investigated with spectrometers and dosimeters.The spectral neutron fluences evaluated from measurements with multisphere systems were recommended to be used for the calculation of dosimetric reference values for...
Content type: Publications -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Content type: Publications -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Content type: Publications -
2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod
The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...
Content type: Publications -
SKI Report 2008:01 Reliability Data for piping Components in Nordic Nuclear Poer Plants "R-Book" Project Phase 1
SKI Report 2008:01 - “Reliability Data for Piping Components in Nordic Nuclear Power Plants - R-Book Project Phase I” – is a planning document for a new R&D project to develop a piping component reliability parameter handbook for use in probabilistic safety assessment (PSA) and related activities. Included in this handbook will be pipe leak failure rates and rupture frequencies that are...
Content type: Publications