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2003:12 Analysis of Critical Issues in Biosphere Assessment Modelling and Site Investigation
The aim of this document is to present a critical review of issues concerned with the treatment of the biosphere and geosphere-biosphere interface in longterm performance assessment studies for nuclear waste disposal in Sweden. The review covers three main areas of investigation: a review of SKB’s plans for undertaking site investigations at candidate locations for the development of a deep...
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 -
2005:15 Radiological Protection in Transition; Proceedings of the XIV Regular Meeting of the Nordic Society for Radiation Protection, NSFS, Rättvik, Sweden, 27-31 August 2005
These proceedings comprise the papers and posters presented at the 14th Regular Meeting of the Nordic Society for Radiation Protection, the theme of which was ‘Radiological protection in transformation’. The traditional ‘Lindell lecture’, presented by H.H. Brunner from Switzerland, highlighted this theme under the title ‘From Pandora’s Box to Sisyphus’. There were sessions on international...
Content type: Publications -
2002:14 Review of C-14 inventory for the SFR facility
The Swedish Radiation Protection Authority (SSI) is currently reviewing SKB’s continuing assessment for disposal of radioactive waste to the SFR facility at Forsmark. Among the wastes disposed are reactor operating wastes. Among the relevant radionuclides is C-14, which is relatively difficult to measure and to control because of its mobility. This report documents a review of the C-14...
Content type: Publications -
In case of an alarm from Ringhals nuclear power plant – What you need to know
SSM English...
Content type: Publications -
2023:05e Radiological Consequences of Fallout from Nuclear Explosions
Summary In this report, Strålsäkerhetsmyndigheten, the Swedish Radiation Safety Authority (SSM), presents an analysis of the potential radiological consequences of fallout from the nuclear explosions at distances between about 10 kilometres and about 300 kilometres from the explosion, and the effect of various protective actions. The contents of the report constitute a knowledge base...
Content type: Publications -
2020:07 Fibre Clogging in Nuclear Power Plants
SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...
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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2025:01 Safety Concept Evaluation with Failure Tolerance Analysis
SSM perspective Background One of the most important design principles to achieve high safety function dependability is the use of redundancy to be single-fault tolerant. In turn, redundancies become effective by applying additional design principles such as physical and functional separation and diversity. License holders of nuclear power reactors must demonstrate that requirements are met,...
Content type: Publications