<p>The Fast Factorized Back Pro jection (FFBP) algorithm is a computationally efficient </p><p>algorithm for image formation in a Very High Frequency Synthetic Aperture Radar (VHF </p><p>SAR) system. In this report an investigation of the feasibility of using an FPGA with a </p><p>hard CPU core to calculate the FFBP in real-time has been done. Two System on a Chip </p><p>designs for this task have been proposed for calculating the FFBP. A simplified version of </p><p>the FFBP has also been implemented in Matlab and used during this pro ject. The result </p><p>is that the computationally intensive parts, such as index generating and interpolation </p><p>calculations, should be implemented in the logic part of the FPGA and the CPU should </p><p>handle scheduling. This kind of modular system is easy to maintain and upgrade.</p>

<p>Generation IV (Gen IV) is a developing new generation of nuclear power reactors which is foreseen to bring about a safer and more sustainable production of nuclear power. A Swedish research program called GENIUS aims at developing the Gen IV technology, with emphasis on lead-cooled fast reactors. The present work is part of the GENIUS project, and deals with safeguards aspects for an envisioned future 100 MW Gen IV demonstration facility including storage and reprocessing plant. Also, the safeguards licensing aspects for the facilities have been investigated and results thereof are presented.</p><p>As a basis for the study, the changed usage and handling of nuclear fuel, as compared to that of today, have been examined in order to determine how today's safeguards measures can be modified and extended to meet the needs of the demonstration facility. Safeguards approaches have been considered for within and between each unit at the demonstration facility, with the main focus on system aspects rather than proposing safeguards instrumentation on a detailed level.</p><p>The proposed safeguards approach include the implementation of well-tried measures that are used at currently existing nuclear facilities as well as suggestions for new procedures. The former include, among others, regular inventory verifications, containment and surveillance measures as well as non-destructive and destructive measurements of nuclear materials. The traditional approaches may be improved and supplemented by modern techniques and approaches such as nuclear forensics, safeguards-by-design and improved on-line monitoring of streams of nuclear material. The safeguards approach for the demonstration facility should be outlined early in the licensing process, such that the facility units can be designed in a way that allows for implementation of adequate safeguards measures with minimal intrusion on the regular activities.</p><p>For operating a nuclear facility in Sweden, two separate permits are required. A license application for a new facility shall be handed both to the Swedish Radiation Safety Authority and to the environmental court, which in parallel prepare for decisions according to the Nuclear Activities Act and the Environmental Code, respectively. In terms of the Swedish legislation, there are no fundamental differences between Gen IV facilities and currently existing plants. However, comprehensive investigations and evaluations would be required in order to license new Gen IV facilities.</p>

Electromagnetic scattering by 3-D arbitrarily shaped homogeneous dielectric objects is characterized. In the analysis, the method of moments is first employed to solve the combined field integral equation for scattering properties of these three-dimensional homogeneous dielectric objects of arbitrary shape. The fast multipole method, and the multi-level fast multipole algorithm are implemented into our codes for matrix-vector manipulations. Specifically, four proposals are made and discussed to increase convergence and accuracy of iterative procedures (conjugate gradient method). Numerical results are obtained using various methods and compared to each other. / Singapore-MIT Alliance (SMA)

Uppsatsen har som syfte att undersöka gällande rätt för internprissatta royaltybetalningar från fast driftställe till moderbolag. Problemet är att varken korrigeringsregeln eller artiklarna 9 och 12 i modellavtalet är tillämpliga. Hur ser möjligheterna ut i den interna rätt för att förhindra att nämnda transaktion utnyttjas i skatteundandragande syfte? Kan artikel 7 i modellavtalet användas för att förhindra sådant? Royalty beskattas som regel i inkomstslaget näringsverksamhet på grund av delaktighetstanken. Den innebär att royaltybetalningar räknas som del i fast driftställe beläget i Sverige. Korrigeringsregeln så väl som artikel 9 fastslås som icke tillämpliga på grund av kravet att avtal föreligger mellan parterna. Artikel 12 kan inte heller tillämpas då royaltyer från fasta driftställen hänvisas till artikel 7. Armlängdsprincipen är den röda tråden inom internprissättning och går ut på att alla transaktioner ska bedömas som om de gjorts mellan skilda enheter eller fristående bolag. Alla lagregler i uppsatsen bygger på denna teori. Artikel 7 i modellavtalet är tillämplig på fasta driftställen och fastslår att inkomster som kan härröras till fasta driftställen ska beskattas i källstaten. I svensk praxis fastslås att korrigeringsregeln ska tillämpas i första hand, men när den möjligheten inte finns är nästa alternativ ofta uttagsbeskattning. Författaren fastslår att felaktigt prissatta royaltybetalningar från fast driftställe till dess moderbolag uppfyller kriterierna för uttagsbeskattning. Diskussionen om nya, alternativa lösningar undersöks där införandet av källskatt respektive slopande av skatten är de ledande åsikterna. Författaren är av åsikten att uttagsbeskattningen utgör gällande rätt men att en förändring bör ske och medan ett slopande av skatten skulle vara den mest enhetliga lösningen, skulle en källskatt innebära ett bättre skydd mot skatteundandragande. / The purpose of the thesis is to investigate the law in force regarding transfer pricing of royalties from permanent establishments (PE) to a parent company. The problem occurs because neither the rule of adjustment (korrigeringsregeln) nor articles 9 and 12 of the OECD model convention are applicable. What pos-sibilities exists in internal Swedish law to prevent the PE and parent company from using transfer pricing of royalty payments to ease the tax burden? Can article 7 be used in hindering capacity in regards to such a transaction? Royalties are generally taxed as income of business due to the principle of par-ticipation (delaktighetestanken), which means that the royalty is considered part of a PE situated in Sweden. The rule of adjustment as well as article 9 are ruled not to be applicable due to the lack of a legally binding contract between the parties. Article 12 point 3 directs royalties from PE’s to article 7 and is therefore not applicable in this situation. A basic principle in regards to transfer pricing is the so called arm’s length method and this is highly important in dealings with PE’s or associated companies to make sure that the transactions are han-dled at market price. The application of article 7 was analyzed with the result that income related to the PE is taxed in the Source state and the Source stated is allowed to adjust the income of the PE if incorrect transfer pricing occurs with the purpose of tax evasion. The Swedish internal tax system has a possibility to extract withdrawal taxes (uttagsbeskattning) in some cases when assets are removed from a company or PE. The conclusion is that these rules apply when incorrectly priced royalties are moved from the PE to the parent company. Alternatives are examined and the author comes to the conclusion that a source tax on royalties would facilitate the application of tax on royalties as well as prevent tax evasion. However, in light of the circumstances that approximately 90% of royalty payments exiting Sweden are submitted to different kinds of ex-emption to taxation, a complete abolishment of taxation on royalties would not be unreasonable.

Generation IV (Gen IV) is a developing new generation of nuclear power reactors which is foreseen to bring about a safer and more sustainable production of nuclear power. A Swedish research program called GENIUS aims at developing the Gen IV technology, with emphasis on lead-cooled fast reactors. The present work is part of the GENIUS project, and deals with safeguards aspects for an envisioned future 100 MW Gen IV demonstration facility including storage and reprocessing plant. Also, the safeguards licensing aspects for the facilities have been investigated and results thereof are presented. As a basis for the study, the changed usage and handling of nuclear fuel, as compared to that of today, have been examined in order to determine how today's safeguards measures can be modified and extended to meet the needs of the demonstration facility. Safeguards approaches have been considered for within and between each unit at the demonstration facility, with the main focus on system aspects rather than proposing safeguards instrumentation on a detailed level. The proposed safeguards approach include the implementation of well-tried measures that are used at currently existing nuclear facilities as well as suggestions for new procedures. The former include, among others, regular inventory verifications, containment and surveillance measures as well as non-destructive and destructive measurements of nuclear materials. The traditional approaches may be improved and supplemented by modern techniques and approaches such as nuclear forensics, safeguards-by-design and improved on-line monitoring of streams of nuclear material. The safeguards approach for the demonstration facility should be outlined early in the licensing process, such that the facility units can be designed in a way that allows for implementation of adequate safeguards measures with minimal intrusion on the regular activities. For operating a nuclear facility in Sweden, two separate permits are required. A license application for a new facility shall be handed both to the Swedish Radiation Safety Authority and to the environmental court, which in parallel prepare for decisions according to the Nuclear Activities Act and the Environmental Code, respectively. In terms of the Swedish legislation, there are no fundamental differences between Gen IV facilities and currently existing plants. However, comprehensive investigations and evaluations would be required in order to license new Gen IV facilities.

With the advent of more powerful, less expensive computing resources, more and more attention is being given to Monte Carlo techniques in design application. In many circles, stochastic solutions are considered the next best thing to experimental data. Statistical uncertainties in Monte Carlo calculations are typically determined by the first and second moments of the tally. For certain types of calculations, there is concern that the uncertainty estimate is significantly non-conservative. This is typically seen in reactor eigenvalue problems where the uncertainty estimate is aggravated by the generation-to-generation fission source. It has been speculated that optimization of the random walk, through biasing techniques, may increase the non-conservative nature of the uncertainty estimate. A series of calculations are documented here which quantify the reliability of the Monte Carlo Neutron and Photon (MCNP) mean and uncertainty estimates by comparing these estimates to the true mean. These calculations were made with a liquid metal fast reactor model, but every effort was made to isolate the statistical nature of the uncertainty estimates so that the analysis of the reliability of the MCNP estimates should be relevant for small thermal reactors as well. Also, preliminary reactor physics calculations for two different special isotope production test assemblies for irradiation in the Fast Flux Test Facility (FFTF) were performed using MCNP and are documented here. The effect of an yttrium-hydride moderator to tailor the neutron flux incident on the targets to maximize isotope production for different designs in different locations within the reactor is discussed. These calculations also demonstrate the useful application of MCNP in design iterations by utilizing many of the codes features. / Graduation date: 1992

The Fast Factorized Back Pro jection (FFBP) algorithm is a computationally efficient algorithm for image formation in a Very High Frequency Synthetic Aperture Radar (VHF SAR) system. In this report an investigation of the feasibility of using an FPGA with a hard CPU core to calculate the FFBP in real-time has been done. Two System on a Chip designs for this task have been proposed for calculating the FFBP. A simplified version of the FFBP has also been implemented in Matlab and used during this pro ject. The result is that the computationally intensive parts, such as index generating and interpolation calculations, should be implemented in the logic part of the FPGA and the CPU should handle scheduling. This kind of modular system is easy to maintain and upgrade.

I den här uppsatsen presenteras en undersökning om bruket av även fast som bisatsinledare iskrift. Syftet med undersökningen är att ta reda på om bruket av bisatsinledaren även fast harbörjat sprida sig från informella texter till mer formella texter. Syftet är också att undersökahållbarheten i ett antagande som förts fram av språkvårdare att fast i även fast uttrycker någotsäkert och verkligt i förhållande till om i även om som uttrycker något osäkert och osannolikt.Metoden består av sökningar i olika databaserade textkorpusar, lucktest till elever i årskurs 9och enkäter till eleverna och deras svensklärare om attityder till även fast i skrift.Resultatet av korpussökningarna visar att även fast verkar ha ökat över tid i vissaskriftsammanhang som i elevers skoltexter och i bloggtexter. Resultatet från elevernaslucktest kan dock varken sägas stödja eller förkasta antagandet att även fast uttrycker någotsäkert och verkligt och även om något osäkert och osannolikt. Däremot visar elevernasattityder till även fast i skrift de problem som den officiella språkvården måste ta ställning tillvid språkförändringar. Man kan antingen hålla fast vid den rådande normen, vid tveksamhethellre välja ett synonymt, men normenligt uttryck eller erkänna att det är en funktionellvariant.

There are three mail types of Botnet: IRC-based Botnet, P2P-based Botnet,Web-based Botnet and they have become major threat to the Internet recently. Web-based Botnet is popular and more harmful to users. The architecture of Web-based Botnet is simpler than P2P-based Botnet, and its malicious traffic can be hidden in a large number of normal traffic. In this study, we built an experimental environment of using malicious bot programs to detect suspicious traffic and malware features. Except network attacking and identity theft, Botnet could also be used by hackers to extend the life time of rouge websites by combining with the technology of Fast Flux Domain. Botnet and the technology of Fast Flux Domain closely link to each other in the real world. Both of Web-based Botnet and Fast Flux Domain technology use HTTP protocol to communicate, and Botnet provides a large number of infected hosts to be Fast Flux Agents which act like a relay station to block the direct link of malicious websites from clients, but completes the mutual connection. In the research, not only the analysis and detection of Web-based Botnet are focused, but also the impact of Fast Flux Domain technology is included. We expect to clear the architecture of Botnet and the technology of Fast Flux Domain, and make the detection mechanism more precisely.

The comparison of nuclear facilities based on their barriers to nuclear material proliferation has remained a difficult endeavor, often requiring expert elicitation for each system under consideration. However, objectively comparing systems using a set of computable metrics to derive a single number representing a system is not, in essence, a nuclear nonproliferation specific problem and significant research has been performed for business models. For instance, Multi-Attribute Utility Analysis (MAUA) methods have been used previously to provide an objective insight of the barriers to proliferation. In this paper, the Proliferation Resistance Analysis and Evaluation Tool for Observed Risk (PRAETOR), a multi-tiered analysis tool based on the multiplicative MAUA method, is presented. It folds sixty three mostly independent metrics over three levels of detail to give an ultimate metric for nonproliferation performance comparison. In order to reduce analysts' bias, the weighting between the various metrics was obtained by surveying a total of thirty three nonproliferation specialists and nonspecialists from fields such as particle physics, international policy, and industrial engineering. The PRAETOR was used to evaluate the Fast Breeder Reactor Fuel Cycle (FBRFC). The results obtained using these weights are compared against a uniform weight approach. Results are presented for five nuclear material diversion scenarios: four examples include a diversion attempt on various components of a PUREX fast reactor cycle and one scenario involves theft from a PUREX facility in a LWR cycle. The FBRFC was evaluated with uranium-plutonium fuel and a second time using thorium-uranium fuel. These diversion scenarios were tested with both uniform and expert weights, with and without safeguards in place. The numerical results corroborate nonproliferation truths and provide insight regarding fast reactor facilities' proliferation resistance in relation to known standards.