Sökning: "MOX"
Visar resultat 6 - 10 av 14 avhandlingar innehållade ordet MOX.
6. De Melo insula Atheniensium cum Meliis disceptatio, primum verbis, mox armis agitata ex Thuc. Lib. V. Capp. LXXXV-CXIII, Svethice versa. Dissertatio philologica, cujus partem priorem ... præside Mag. Joseph. Otto. Höijer ... pro gradu philosophico p. p. auctor John Unæus Stip. Reg. Norrlandus. In Audit. Gust. die VIII Junii MDCCCXXX. H. A. M. S
Sammanfattning : .... LÄS MER
7. De Melo insula Atheniensium cum Meliis disceptatio, primum verbis, mox armis agitata ex Thuc. Lib. V. Capp. LXXXV-CXIII, Svethice versa. Dissertatio philologica, cujus partem posteriorem ... præside Mag. Joseph. Otto. Höijer ... pro gradu philosophico p. p. auctor Andreas Augustus Fris stip. Palmb. Sudermanno-Nericius. In Audit. Gust. die VIII Junii MDCCCXXX. H. P. M. S
Sammanfattning : .... LÄS MER
8. Change detection in metal oxide gas sensor signals for open sampling systems
Sammanfattning : This thesis addresses the problem of detecting changes in the activity of a distant gas source from the response of an array of metal oxide (MOX) gas sensors deployed in an Open Sampling System (OSS). Changes can occur due to gas source activity such as a sudden alteration in concentration or due to exposure to a different compound. LÄS MER
9. Alternative Energy Harvesting and Conversion Systems Based on Nanostructured Heterostructures
Sammanfattning : Conversion and storage of the solar radiation into applicable forms of energy, using ubiquitous materials is of central importance that quests several disciplinary fields in both applied technology and fundamental science. Harnessing the solar energy received by the earth has the potential to replace the current sources of energy and it is imperative for sustainable development. LÄS MER
10. Transmutation of Americium in Fast Neutron Facilities
Sammanfattning : In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code. The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters. LÄS MER