Din avgränsning ger 332 träffar.
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2009:19 Review of SKB’s Quality Assurance Programme
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...
Innehållstyp: Publikationer -
2008:10 International Expert Review of SR-Can: Engineered Barrier Issues
The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...
Innehållstyp: Publikationer -
2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption
For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...
Innehållstyp: Publikationer -
2007:10 DECOVALEX-THMC - Task D
The DECOVALEX project is an international cooperative project initiated by SKI, the Swedish Nuclear Power Inspectorate, with participation of about 10 international organizations. The name DECOVALEX stands for DEvelopment of COupled models and their VALidation against Experiments. The general goal of this project is to encourage multidisciplinary interactive and cooperative research on...
Innehållstyp: Publikationer -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Innehållstyp: Publikationer -
2005:44 Urananrikning med gascentrifugering
Den nu resulterande rapporten berör kortfattat teorin och några generella principer för gascentrifugering, vilken utrustning som kan komma ifråga, indikatorer på anrikning med gascentrifugering, mm. Vi har valt att låta rapporten vara översiktlig utan att gå in på detaljer. Detta för att inte sprida information som kan vara känslig ur kommersiell...
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 -
2011:02 The Back-End of the Nuclear Fuel Cycle in Sweden, Considerations for safeguards and data handling
The report is a compilation report consisting of three papers. A safeguards approach for the planned encapsulation facility and the operating final repository is presented in paper 1. Special considerations concerning safeguards for the final disposal process have been discussed and incorporated into the approach. Paper 2 defines the spent fuel data that must be secured, for safeguards...
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 -
2015:15 Användning av låg- och höganrikat uran – en studie från ett icke-spridningsperspektiv
Höganrikat uran definieras som uran med en anrikning av 235U på minst 20 %. Att minska eller helt eliminera det civila användandet av hoöanrikat uran är ett viktigt led i internationellt icke-spridningsarbete. Till skillnad från plutonium är höganrikat uran inte en biprodukt utan framställs för ett specifikt ändamål. Detta innebär att...
Innehållstyp: Publikationer