Din avgränsning ger 751 träffar.
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2007:05 Development of an Input Model to MELCOR 1.8.5 for Oskarshamn 3 BWR
An input model has been prepared for the Oskarshamn 3 rector. Demonstrations calculations, at current nominal operating conditions in Oskarshamn 3 for 3300 MW thermal power, were performed for three cases: (1) initial, steady-state conditions, (2) total loss of AC power and (3) large steam line LOCA. The results are presented in the report. 200 Lars Nilsson SKI English An input model has been...
Innehållstyp: Publikationer -
2013:02 Forskningsreaktorer - en analys med fokus på icke-spridning och exportkontroll
Den nu resulterande rapporten berör kortfattat några olika typer av forskningsreaktorer liksom några av deras viktigaste användningsområden. Dessutom berörs reaktorernas användbarhet för plutoniumproduktion samt några indikationer på reaktordrift. Vi har valt att låta rapporten vara översiktlig utan att gå in på detaljer för...
Innehållstyp: Publikationer -
1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy
A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...
Innehållstyp: Publikationer -
2008:18 Concerns when designing a safeguards approach for the back-end of the Swedish nuclear fuel cycle
Sweden has for many years collected the spent nuclear fuel originating from nuclear power plants. This fuel must at all times be kept under supervision to render a diversion impossible; this is of course due to the possibility to make weapons from the material. One idea is to keep the nuclear material in a repository deep under the ground; this is not only to keep the material safe from theft...
Innehållstyp: Publikationer -
98:35 Nuclear Fuel Assembly Assessment Project and Image Categorization
C. S. Lindsey (1), T. Lindblad (1), K. Waldemark (1), L. Hildningsson (2). (1) Royal Institute of Technology, Stockholm, Sweden. (2) Swedish Nuclear Power Inspectorate, Stockholm, Sweden. July 1998 SKI English...
Innehållstyp: Publikationer -
2008:21 Sammanfattande bedömning av strålskyddet vid de kärntekniska anläggningarna i Sverige 2007
I rapporten redovisas SSI:s bedömning av de verksamheter som bedrivits under 2007 vid de svenska kärntekniska anläggningarna. Bedömningen är ett resultat av tillsyn mot anläggningarna under året. Peter Hofvander, Lars Malmqvist, maria Lüning, Svante Ernberg, Helén Wijk, Henrik, Efraimsson, Anki Hägg, Karin Fritioff och Anders Wiebert SSI Svenska...
Innehållstyp: Publikationer -
2008:10 User’s manual for Ecolego Toolbox and the Discretization Block
The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...
Innehållstyp: Publikationer -
2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment
An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...
Innehållstyp: Publikationer -
2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment
With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...
Innehållstyp: Publikationer -
2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository
PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...
Innehållstyp: Publikationer