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Bilaga 3 - Spridnings- och dosberäkningar
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Anmälan om samråd vid säkerhetsskyddsavtal
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Komplettering av ansökan.PDF
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2020:15e Protective Actions in Nuclear or Radiological Emergencies - Planning Basis for Events in Emergency Preparedness Category IV
In this report, the Swedish Radiation Safety Authority (SSM) presents planning basis for protective actions in the event of nuclear or radiological emergencies in connection with activities and acts in emergency preparedness category IV. Activities and acts encompass events in activities with ionizing radiation that are not conducted in a specifically defined location as well as antagonistic...
Content type: Publications -
2023:03 A novel method for retrospective analysis regarding appropriateness of radiological examinations
SSM perspective Background The use of X-ray diagnostic examinations, especially computed tomography, has increased in recent decades and it is essential that this increase is justified and contribute to a better care of the patients. There are many reasons to refrain from performing inappropriate radiological examinations, including not to expose patients to unnecessary ionising radiation. In...
Content type: Publications -
2023:02 Investigation of risk assessment for decommissioning waste to Fortum’s landfill at Norrtorp
Shulan Xu, Ryk Klos SSM English...
Content type: Publications -
2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage
SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...
Content type: Publications -
2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay
SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...
Content type: Publications