Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Marcus Hedberg"'
Publikováno v:
Chemical Engineering & Technology. 44:1075-1083
A comparative study of chemical looping combustion (CLC) with paper, plastic, and coal as fuel was carried out. Experiments were performed in a laboratory fluidized-bed reactor by alternating between reduction and oxidation cycles. The results obtain
Publikováno v:
Nuclear Science and Engineering. 193:1255-1264
Uranium nitride (UN) is considered as nuclear reactor fuel because of, among other reasons, its high uranium density and its high thermal conductivity. Its main drawback is that it relatively easil...
Autor:
Diogo Ribeiro Costa, Marcus Hedberg, Denise Adorno Lopes, Mathieu Delmas, Simon C. Middleburgh, Janne Wallenius, Pär Olsson
Publikováno v:
Journal of Nuclear Materials. 567:153845
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry
Nuclear energy has been a part of the energy mix in many countries for decades. Today in principle all power producing reactors use the same techniqe. Either PWR or BWR fuelled with oxide fuels. This choice of fuel is not self evident and today there
Publikováno v:
Journal of Nuclear Materials. 555:153150
Uranium nitride is being investigated as a replacement for UO2 as it shows enhanced thermal properties and seems to be a promising accident tolerant fuel (ATF) candidate. The main drawback of UN fuel is its innate low oxidation resistance in air/wate
Autor:
Christian Ekberg, Marcus Hedberg
Publikováno v:
Journal of Nuclear Materials. 482:156-162
Fabrication of plutonium containing fuels through the internal gelation method has mostly been studied in mixed metal systems such as U, Pu or Zr, Pu. In this work production of undiluted PuN has been performed by carbothermal reduction on both oxide
Autor:
Marcus Hedberg, Janne Wallenius, Denise Adorno Lopes, D. Costa, Pär Olsson, Simon C. Middleburgh
Publikováno v:
Journal of Nuclear Materials. 544:152700
Composite fuels such as UN-UO2 are being considered to address the lower oxidation resistance of the UN fuel from a safety perspective for use in light water reactors, whilst improving the in-reactor behaviour of the more ubiquitous UO2 fuel. An inno
Publikováno v:
Journal of Nuclear Materials. 479:137-144
Inert matrix fuel is a fuel type where the fissile material is blended with a solid diluent material. In this work zirconium carbonitride microspheres have been produced by internal sol gel technique, followed by carbothermal reduction. Material nitr
Autor:
Marcus Hedberg, Christian Ekberg
Publikováno v:
Journal of Nuclear Materials. 479:608-615
Sol-gel based techniques are one way to lower the handling of highly radioactive powders when producing transuranium-containing fuel. In this work inert matrix (Zr0.6,Pu0.4)N fuel has been produced by internal gelation followed by carbothermal reduct
Autor:
Emma Aneheim, Marcus Hedberg
Publikováno v:
Procedia Chemistry. 21:231-238
Nitride fuels have been regarded as one viable fuel option for Generation IV reactors due to their positive features compared to oxides. To be able to close the fuel cycle and follow the Generation IV concept, nitrides must, however, demonstrate thei