Zobrazeno 1 - 10
of 39
pro vyhledávání: '"Karel Lemmens"'
Publikováno v:
MRS Advances. 7:95-99
In the context of the geological disposal of vitrified radioactive waste, cracks are expected at the full scale of the glass blocks. To simulate glass alteration in cracks, static dissolution experiments were conducted with confined SM539 glass powde
Autor:
Christian Schreinemachers, Gregory Leinders, Thierry Mennecart, Christelle Cachoir, Karel Lemmens, Marc Verwerft, Felix Brandt, Guido Deissmann, Giuseppe Modolo, Dirk Bosbach
Publikováno v:
MRS advances 7, 100-104 (2022). doi:10.1557/s43580-022-00220-7
Autoclave leaching experiments are conducted on three well-characterised, irradiated, and cladded mixed oxide fuel-rod segments with burnups ranging from 29 GWd/tHM to 52 GWd/tHM to investigate the instant release fraction of fission gases and long-l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::66303f8cdf8ae2c711f4a12314e0bf1b
https://hdl.handle.net/2128/31627
https://hdl.handle.net/2128/31627
Autor:
Christian Schreinemachers, Giuseppe Modolo, Gregory Leinders, Thierry Mennecart, Christelle Cachoir, Karel Lemmens, Marc Verwerft, Guido Deissmann, Dirk Bosbach
Publikováno v:
45th Scientific Basis for Nuclear Waste Management Symposium, SBNWM, virtual event, Germany, 2021-10-25-2021-10-28
Theslides werepresented at the 45th Scientific Basis for Nuclear Waste Management SymposiumonOctober 27, 2021. Abstract Disposal in a deep geological repository (DGR) based on a multibarrier concept is considered as the safest and most sustainable op
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::acc469d3fdc74c7789b597ea9763dd50
Autor:
Sanheng Liu, Colleen Mann, Claire L. Corkhill, Jeremy R. Eskelsen, Eric M. Pierce, Karel Lemmens, Karine Ferrand
Publikováno v:
npj Materials Degradation, Vol 3, Iss 1, Pp 1-9 (2019)
Understanding the corrosion of nuclear waste glass is critical to predicting its safe disposal within a geological facility. The corrosion mechanisms and kinetics of the International Simple Glass, a simplified version of high-level nuclear waste gla
Autor:
Karine Ferrand, Sébastien Caes, Jenna Poonoosamy, Karel Lemmens, Juri Barthel, Felix Brandt, Dirk Bosbach, Wouter Van Van Renterghem, Martina Klinkenberg
Publikováno v:
Interdisciplinary research symposium On the safety of nuclear disposal practices 2021, safeND, Berlin, online, Germany, 2021-11-10-2021-11-12
Immobilization of high-level and intermediate-level nuclear wastes by vitrification in borosilicate glass is a well-established process. There is a consensus between the waste management agencies of many countries and many experts that vitrified nucl
Autor:
Dirk Bosbach, Sébastien Caes, Wouter Van Van Renterghem, Juri Barthel, Jenna Poonoosamy, Karel Lemmens, Karine Ferrand, Martina Klinkenberg, Felix Brandt
Publikováno v:
Materials
Volume 14
Issue 5
Materials 14(5), 1254-(2021). doi:10.3390/ma14051254
Materials, Vol 14, Iss 1254, p 1254 (2021)
Volume 14
Issue 5
Materials 14(5), 1254-(2021). doi:10.3390/ma14051254
Materials, Vol 14, Iss 1254, p 1254 (2021)
Static dissolution experiments were carried out with the reference International Simple Glass under hyperalkaline pH at 70 °C and very high SA/V ratio. Three aspects of glass dissolution behavior were investigated, (1) the rate drop regime and the r
Autor:
Gregory Leinders, Jan Eysermans, Thierry Mennecart, Christelle Cachoir, Karel Lemmens, Christian Schreinemachers, Guido Deissmann, Giuseppe Modolo, Dirk Bosbach, Marc Verwerft
Publikováno v:
Topfuel 2021, Santander, Spain, 2021-10-24-2021-10-28
Technical paper submitted for peer-review, accepted, and presented at the 2021 Topfuel conference (October 24-28, 2021). The conference was hosted as a hybrid event with on-site attendance (Santander, Spain) and remote attendance via a web applicatio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2414a33357063a314b2d6cd4400b8c3b
https://hdl.handle.net/2128/28908
https://hdl.handle.net/2128/28908
Publikováno v:
Journal of Nuclear Materials. 557:153257
For the safety assessment of Spent Nuclear Fuel (SNF) in disposal conditions, it is crucial to determine the fast release of the potentially critical radionuclides (e.g. 129I, 137Cs, 99Tc, 93Mo, 90Sr…) upon contact with water. To underpin the quant
Publikováno v:
MRS Advances. 2:661-667
The International Simple Glass (ISG) is considered as reference benchmark glass and is used in the frame of an international collaboration for the study of the dissolution mechanisms of high-level vitrified nuclear waste.In this work the forward diss
Publikováno v:
MRS Advances. 1:4139-4145
In the framework of the Euratom FIRST-Nuclides program, SCK•CEN conducted leaching experiments on a PWR UOX fuel, taken from the Belgian Tihange 1 reactor, with an average rod burnup of 50 MWd/kgHM in order to determine the rapid release of some of