Research 2010:33 Report number: 2010:33 ISSN: 2000-0456 Availableatwww.stralsakerhetsmyndigheten.se Lineament interpretation Short review and methodology Authors: Sven Tirén Title: Lineament interpretation Short review and methodology Report number: 2010:33 Author: Sven Tirén GEOSIGMA AB Date: November 2010 This report concerns a study which has been conducted for the Swedish Radiation Safety Auth
[en] In this report, we have reviewed the basic features of the accident processes and radioactivity releases that occurred in the Chernobyl accident (1986) and in the Fukushima-1 accident (2011). The Chernobyl accident was a power-surge accident that was caused by a failure of control of a fission chain reaction, which instantaneously destroyed the reactor and building, whereas the Fukushima-1 ac
[en] The author describes the different circumstances that, in a reactor accident, lead to varying compositions of radionuclides being released, depending on the operational state and exact sequence of events. The range of radionuclides released is so variable that it is not possible to know in advance either what will be released or what exposure pathways will be important. This is illustrated wi
[en] It is argued that the scientific foundations for dose-response relationships for low radiation doses as recommended by e.g. ICRP are questionable, based on obsolete apprehensions of the mechanisms underlying the transformation of a normal cell into a malignant phenotype. The author questions that an extremely complex phenomenon as the dose-response of radiogenic cancer is a linear, non-thresh
[en] The paper presents calculated inventories of radio nuclides of the Fukushima Dai-ichi NPP. In a first step the calculation method and the computer code system were adjusted and evaluated by performing a Benchmark with experimental results. Further, the fuel rods in the UO2- and MOX fuel elements were characterized and burn up and decay calculations were performed for the spent fuel at the dif
[en] The paper presents calculated inventories of radio nuclides of the Fukushima Dai-ichi NPP. In a first step the calculation method and the computer code system were adjusted and evaluated by performing a Benchmark with experimental results. Further, the fuel rods in the UO2- and MOX fuel elements were characterized and burn up and decay calculations were performed for the spent fuel at the dif
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