Neutronic aspects of inert matrix fuels for application in ADS
2003 (English)In: Journal of Nuclear Materials, ISSN 0022-3115, E-ISSN 1873-4820, Vol. 320, no 02-jan, 142-146 p.Article in journal (Refereed) Published
Accelerator driven systems may operate on uranium or thorium free fuels. In order to guarantee the stability of such fuels at high temperatures, the use of inert matrices is foreseen. In the present study, safety parameters of 800 MWthADS cores operating on oxide and nitride fuels with high americium content are investigated for a representative range of pin and core geometries. It is shown that among the inert matrices investigated, chromium yields the lowest void worth, hafnium nitride the highest fission probability for americium and magnesia the highest burnup potential.
Place, publisher, year, edition, pages
2003. Vol. 320, no 02-jan, 142-146 p.
Engineering and Technology
IdentifiersURN: urn:nbn:se:kth:diva-22653ISI: 000184038200019OAI: oai:DiVA.org:kth-22653DiVA: diva2:341351
QC 20100525 NR 201408042010-08-102010-08-102012-01-31Bibliographically approved