Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Christelle Cachoir"'
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:
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
Autor:
Kevin Govers, Lesley Adriaensen, Andrew Dobney, Mireille Gysemans, Christelle Cachoir, Marc Verwerft
Publikováno v:
EPJ Nuclear Sciences & Technologies. 8:18
In order to derive the burnup of spent nuclear fuel from the concentration of selected fission products (typically the Nd isotopes and 137Cs), their irradiation-averaged fission yields need to be known with sufficient accuracy, as they evolve with th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ca2544c710b63e050775f738d8feca9
https://doi.org/10.1051/epjn/2022018
https://doi.org/10.1051/epjn/2022018
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::63f527332aac40940e806c29292998c6
https://doi.org/10.1016/j.jnucmat.2021.153257
https://doi.org/10.1016/j.jnucmat.2021.153257
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::76fadc036161256abe277d9a33048a8e
https://doi.org/10.1557/adv.2017.201
https://doi.org/10.1557/adv.2017.201
Publikováno v:
Procedia Chemistry. 21:306-313
Leaching experiments were performed with depleted UO2 powders in tetramethylammonium solutions (TMA-OH) at pH 13.5 and 12.5, and at different UO2 surface area to volume of solution (SA/V) ratio's to determine the solubility and the dissolution kineti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ce8ef5c59698ed33b9edff8b3aebe5f5
https://doi.org/10.1016/j.proche.2016.10.043
https://doi.org/10.1016/j.proche.2016.10.043
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 304:61-66
To assess the long-term behaviour of spent fuel in conditions of the Belgian Supercontainer design, dissolution tests were performed to determine the solubility and dissolution rate of depleted and Pu-doped UO2 in synthetic cement waters. The results
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb72da7d66b7f4f947204a473ab63a82
https://doi.org/10.1007/s10967-014-3667-z
https://doi.org/10.1007/s10967-014-3667-z
Publikováno v:
MRS Proceedings. 1665:267-273
To assess the stability of spent fuel in the highly alkaline chemical environment of the Belgian Supercontainer design, static leach experiments were performed with depleted UO2 and 238Pu-doped UO2 at different SA/V ratios for 1.5 years in cement wat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b8e78b4db2591f63733c2eb3603a8224
https://doi.org/10.1557/opl.2014.654
https://doi.org/10.1557/opl.2014.654
Autor:
Laurence Bois, Christelle Cachoir, Patrick Trocellier, C Tiffreau, S. Guilbert, V Badillo, Jean-Paul Gallien, F. Mercier, N Barré
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 158:511-516
Radioactive waste management is one of the major technical and scientific challenge to be solved by industrialized countries near the beginning of the 21st century. Relevant questions arise about the extrapolation of the long term-behavior of materia
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2fe4823d6ea7d41d3e05d9584d677b2
https://doi.org/10.1016/s0168-583x(99)00391-2
https://doi.org/10.1016/s0168-583x(99)00391-2