Christelle Cachoir

Research output

Research output per year 2000 2006 2012 2015 2019 2022

• 14 In-proceedings paper
• 9 ER - External report
• 5 Article
• 1 BLG - Open report

Research output per year

Research output per year

Search results

• 2019

  First phase of the spent fuel autoclave leaching experiments (SF-ALE) at sck cen

  Mennecart, T., Leinders, G., Cachoir, C., Cornelis, G., Verpoucke, G., Modolo, G., Bosbach, D., Lemmens, K. & Verwerft, M., 22 Sep 2019, GLOBAL/TOPFUEL 2019. American Nuclear Society, p. 1-8 8 p.

  Research output › peer-review

  Open Access

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  53 Downloads (Pure)
• 2016

  Uranium dissolution in hyperalkaline TMA-OH solutions: Preliminary results

  Cachoir, C., Salah, S., Mennecart, T. & Lemmens, K., 1 Dec 2016, ATALANTE 2016 INTERNATIONAL CONFERENCE ON NUCLEAR CHEMISTRY FOR SUSTAINABLE FUEL CYCLES: 5th International ATALANTE International Conference on Nuclear Chemistry for Sustainable Fuel Cycles. Vol. 21. p. 306-313 (Procedia Chemistry).

  Research output › peer-review

  Open Access
• 2012

  Characterisation of SCK-CEN fuel samples used for leach tests in FIRST-Nuclides

  Govers, K., Verwerft, M., Van Renterghem, W., Lemmens, K., Mennecart, T., Cachoir, C., Adriaensen, L., Dobney, A. & Gysemans, M., 10 Oct 2012, 1st Annual Workshop Proceedings - 7th EC - FP First-Nuclides. Budapest, Hungary, p. ST61-ST67

  Research output › peer-review

• Corrosion behavior of spent nuclear fuel in high pH solutions – Effect of hydrogen

  Loida, A., Gens, R., Bube, C., Lemmens, K., Cachoir, C., Mennecart, T. & Kienzler, B., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 119-124 (MRS Symposium Proceedings; no. 1475).

  Research output › peer-review

• Effect of a cement buffer on Spent Fuel dissolution

  Mennecart, T., Cachoir, C., Lemmens, K., Gielen, B., Vercauter, R. & Druyts, F., Mar 2012, Cementitious materials in safety cases for geological repositories for radioactive waste: role, evolution and interaction. Paris, France, p. 199-203 (NEA/RWM report; no. NEA/RWM/R(2012)3).

  Research output › peer-review

• Interaction of cementitious materials with high-level waste matrices

  Lemmens, K., Cachoir, C., Ferrand, K., Mennecart, T., Gielen, B., Vercauter, R. & Druyts, F., Mar 2012, Cementitious materials in safety cases for geological repositories for radioactive waste: role, evolution and interaction. Paris, France, p. 129-130 (NEA/RWM report; no. NEA/RWM/R(2012)3).

  Research output › peer-review

• Spent fuel dissolution in Belgian Supercontainer conditions: Source term and compatibility

  Lemmens, K., Mennecart, T., Cachoir, C. & Kursten, B., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 131-136 (MRS Symposium Proceedings; no. 1475).

  Research output › peer-review

• UO2 dissolution in high pH conditions of the Belgian Supercontainer

  Mennecart, T., Cachoir, C. & Lemmens, K., Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, p. 293-298 (MRS Symposium Proceedings; no. 1475).

  Research output › peer-review

• 2011

  The interaction between nuclear waste glass and cement

  Ferrand, K., Lemmens, K., Depierre, S. & Cachoir, C., Oct 2011, Proceedings 1st International Symposium on Cement-based Materials for Nuclear Wastes. NUWCEM 2011. Marcoule, France, p. 1-11

  Research output › peer-review

• 2009

  Corrosion Behavior of High Burnup Spent Fuel in Highly Alkaline Solutions

  Loida, A., Gens, R., Metz, V., Lemmens, K., Cachoir, C., Mennecart, T., Kienzler, B. & Ferrand, K., Dec 2009, Scientific Basis for Nuclear Waste Management XXXIII. Symposium Proceedings. Volume 1193. Warrendale, PA, United States, p. 597-604 (Materials Research Society proceedings; no. Volume 1193).

  Research output › peer-review

• 2008

  The strategy of the Belgian nuclear research centre in the area of high level waste form compatibility research

  Lemmens, K., Cachoir, C., Valcke, E., Ferrand, K., Aertsens, M. & Mennecart, T., May 2008, The 11th International Conference on Environmental Remediation and Radioactive Waste Management. Fairfield, NJ, United States, p. 1-8

  Research output › peer-review

• 2007

  Dissolution behaviour of UO2 in anoxic conditions. Comparison of Ca-bentonite and Boom Clay

  Mennecart, T., Cachoir, C., Lemmens, K., Volckaert, G. & Wang, L., Dec 2007, Scientific Basis for Nuclear Waste Management XXX, MRS Proceedings Volume 985. Warrendale, Pennsylvania, United States, p. 39-42

  Research output › peer-review

• 2006

  Mechanisms governing the release of radionuclides from spent nuclear fuel in geological repository: Major outcomes of the European Project SFS

  Poinssot, C., Ferry, C., Grambow, B., Kelm, M., Spahiu, K., Martinez, A., Johnson, L., Cera, E., de Pablo, J., Quinones, J., Wegen, D., Lemmens, K., McMenamin, T. & Cachoir, C., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 421-432

  Research output › peer-review

• Static dissolution tests of alpha-doped UO2 under repository relevant conditions: Influence of Boom Clay and alpha-activity on fuel dissolution rates

  Salah, S., Cachoir, C., Lemmens, K. & Maes, N., Jun 2006, Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, p. 481-488

  Research output › peer-review