Thierry Mennecart

Research output

Research output per year 2007 2012 2015 2022 2024 2024

• 14 In-proceedings paper
• 12 Article
• 11 ER - External report
• 4 Third partyreport

Research output per year

Research output per year

Search results

• 2024

  Characterisation of high burnup spent mixed oxide fuel after leaching at hyperalkaline pH in a reducing environment

  Schreinemachers, C., Leinders, G., Van Eyken, J., Mennecart, T., Cachoir, C., Lemmens, K., Verwerft, M., Deissmann, G., Bosbach, D. & Modolo, G., Jun 2024, In: MRS Advances. 9, 7, p. 351-356 6 p.

  Research output › peer-review

  Open Access

• Effect of hydrogen gas and leaching solution on the fast release of fission products from two PWR fuels

  Mennecart, T., Iglesias Pérez, L., Herm, M., König, T., Leinders, G., Cachoir, C., Lemmens, K., Verwerft, M., Metz, V., González-Robles, E., Meert, K., Vandoorne, T. & Gaggiano, R., 1 Jan 2024, In: Journal of Nuclear Materials. 588, 17 p., 154811.

  Research output › peer-review

  Open Access

• Electrochemical study of the influence of pH and carbonate species concentration on the dissolution of depleted UO₂

  Caes, S., Cachoir, C., Mennecart, T., Kursten, B. & Lemmens, K., 2024, In: MRS Advances.

  Research output › peer-review

• Fission product release from spent nuclear UOX fuel dissolution: Comparison between anoxic and reducing conditions and impact of pH

  Mennecart, T., Cachoir, C., Lemmens, K., Gaggiano, R., Meert, K. & Vandoorne, T., Jun 2024, In: MRS Advances. 9, 7, p. 363-367 5 p.

  Research output › peer-review

  Open Access

• Submitted scientific journal papers about the RSOW stability and durability tests after reconditioning: PREDIS Deliverable 6.8

  Mennecart, T., 28 Aug 2024, Predis. 9 p. (PREDIS Reports; no. D6.8)

  Research output › peer-review

  Open Access

  File
• 2023

  Draft governance implementation plan: PREDIS Milestone 13

  Holt, E., Abdelouas, A., Banford, A., Bruggeman, C., Carbol, P., Fournier, M., Hamadache, K., Mennecart, T. & Niederleithinger, E., 28 Feb 2023, Predis. 10 p. (PREDIS Reports; no. Predis - Milestone 13)

  Research output › peer-review

  Open Access

  File
• 2022

  Caesium and iodine release from spent mixed oxide fuels under repository relevant conditions - Initial leaching results

  Schreinemachers, C., Leinders, G., Mennecart, T., Cachoir, C., Lemmens, K., Verwerft, M., Brandt, F., Deissmann, G., Modolo, G. & Bosbach, D., 9 Feb 2022, In: MRS Advances. p. 1-5 5 p.

  Research output › peer-review

  Open Access

• LCA Case Study Input to WP2: PREDIS Milestone 44

  Mennecart, T., Nonnet, H., Walling, S., Mossini, E. & Stamford, L., 25 Aug 2022, Predis. 4 p. (PREDIS Reports; no. Milestone 44)

  Research output › peer-review

  Open Access

  File
  1 Downloads (Pure)

• Predisposal conditioning, treatment, and performance assessment of radioactive waste streams

  Holt, E., Oksa, M., Nieminen, P., Abdelouas, A., Banford, A., Fournier, M., Mennecart, T. & Niederleithinger, E., 14 Dec 2022, In: EPJ Nuclear Science & Technologies. 8, 6 p., 40.

  Research output › peer-review

  Open Access

• Pyrite oxidation by nitrate and nitrite in sodium bicarbonate solution under anoxic and abiotic conditions

  Hendrix, K., Bleyen, N., Mennecart, T., Eloy, P., Valcke, E. & Gaigneaux, E. M., 1 Feb 2022, In: Applied Geochemistry. 137, p. 1-16 16 p., 105203.

  Research output › peer-review

  Open Access

• SF-ALE report: Report – Phase I

  Mennecart, T., 15 Sep 2022, SCK CEN. 49 p. (SCK CEN Reports; no. ER-0759)

  Research output › peer-review

• Surface-mediated redox activity in the Pyrite – Nitrate/nitrite – Hydrogen system under conditions relevant for the geological disposal of bituminized waste in Boom Clay

  Hendrix, K., Bleyen, N., Mennecart, T., Gaigneaux, E. M., Eloy, P. & Valcke, E., 1 Aug 2022, In: Applied Geochemistry. 143, August 2022, p. 1-13 13 p., 105386.

  Research output › peer-review
• 2021

  Evolution of the uranium concentration in dissolution experiments with Cr (Pu) doped UO2 in reducing conditions at SCK CEN

  Cachoir, C., Mennecart, T. & Lemmens, K., 18 Mar 2021, In: MRS Advances. 6, p. 84-89 6 p.

  Research output › peer-review

  Open Access

• Fast release from clad and declad spent UOX PWR fuel segments in a bicarbonate solution under anoxic conditions

  Mennecart, T., Cachoir, C. & Lemmens, K., 3 Sep 2021, In: Journal of Nuclear Materials. 557, p. 1-10 10 p., 153257.

  Research output › peer-review

  Open Access

• Gap Analysis - 31.5.2021 version Final: PREDIS Deliverable 2.2

  Schatz, T., Holt, E., Grambow, B., Fournier, M., Lambertin, D., Mennecart, T. & Niederleithinger, E., 31 May 2021, Predis. 68 p. (PREDIS Reports; no. D2.2)

  Research output › peer-review

  Open Access

  File
• 2019

  Dissolution behaviour of spent nuclear fuel at highly alkaline conditions: Phenomenological synthesis report

  Lemmens, K., Cachoir, C. & Mennecart, T., 1 Jan 2019, SCK CEN. 103 p. (SCK•CEN Reports; no. ER-0505)

  Research output › peer-review

  Open Access

  File
  284 Downloads (Pure)

• 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

  File
  62 Downloads (Pure)

• Sodium azide used as microbial inhibitor caused unwanted by-products in anaerobic geochemical studies

  Hendrix, K., Bleyen, N., Mennecart, T., Bruggeman, C. & Valcke, E., 1 Aug 2019, In: Applied Geochemistry. 107, p. 120-130 11 p.

  Research output › peer-review

  Open Access
• 2018

  Instant Release Fraction (Source and Expert ranges) for SFC-1: UOX 50 and 60 GWd/tHM MOX 50 GWd/tHM. Status 2011

  Cachoir, C. & Mennecart, T., 1 Mar 2018, SCK CEN. 65 p. (SCK•CEN Reports; no. ER-0166)

  Research output › peer-review

  Open Access

  File
  69 Downloads (Pure)
• 2017

  Dynamic experiments: Intermediate topical report

  Mennecart, T., Cachoir, C. & Lemmens, K., 1 Jun 2017, SCK CEN. (SCK•CEN Reports; no. SCK•CEN ER-0385)

  Research output › peer-review

  Open Access

  File
  33 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

• XPS topical report

  Mennecart, T., Elia, A. (Peer reviewer), Valcke, E. (Peer reviewer) & Jacops, E. (Peer reviewer), 1 Jul 2016, SCK CEN. 54 p. (SCK•CEN Reports; no. SCK•CEN ER-0330)

  Research output › peer-review

  Open Access

  File
  74 Downloads (Pure)
• 2015

  Executive summary of the level 5 report -Spent fuel dissolution in supercontainer conditions- reporting period 2009-2012 / ER-231

  Cachoir, C. & Mennecart, T., Mar 2015, 0 ed. SCK CEN. 49 p. (SCK•CEN Reports; no. ER-285)

  Research output › peer-review

  Open Access

  File
  44 Downloads (Pure)

• Influence of the alpha radiation on the UO₂ dissolution in high pH cementitious waters

  Mennecart, T., Cachoir, C. & Lemmens, K., 1 Apr 2015, In: Journal of Radioanalytical and Nuclear Chemistry. 304, 1, p. 61-66 6 p.

  Research output › peer-review
  5 Scopus citations

• “Spent fuel Dissolution in Supercontainer conditions” Period 2012-2014

  Cachoir, C., Mennecart, T. & Jobbágy, V. (Peer reviewer), Sep 2015, 0 ed. SCK CEN. 70 p. (SCK CEN Reports; no. ER-275)

  Research output › peer-review

  Open Access

  File
  50 Downloads (Pure)

• “Spent fuel Dissolution in Supercontainer conditions” Reporting period 2009-2012. Level 5 Report “Spent fuel Dissolution in Supercontainer conditions” RP.W&D.0060: Programme 2009-2014. Final report.

  Cachoir, C. & Mennecart, T., Jan 2015, 0 ed. SCK CEN. 526 p. (SCK•CEN Reports; no. ER-231)

  Research output › peer-review

  Open Access

  File
  86 Downloads (Pure)
• 2014

  Effect of cement water on UO₂ solubility

  Cachoir, C., Mennecart, T. & Lemmens, K., 2014, Scientific Basis for Nuclear Waste Management XXXVII. Duro, L., Gimenez, J., Casas, I. & de Pablo, J. (eds.). MRS - Materials Research Society, Vol. 1665. p. 267-273 7 p. (Materials Research Society Symposium Proceedings; vol. 1665).

  Research output › peer-review
  1 Scopus citations

• Estimation of the effective surface area of UOX (MOX) spent fuel in Supercontainer disposal conditions (status 2010)

  Cachoir, C. & Mennecart, T., Dec 2014, 1 ed. SCK CEN. 33 p. (SCK•CEN Reports; no. ER-142)

  Research output › peer-review

• FIRST-Nuclides: Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel

  Kienzler, B., Metz, V., González-Robles, E., Duro, L., Vals, A., Wegen, D., Carbol, P., Serrano-Purroy, D., Curtius, H., Günther-Leopold, I., Froideval Zumbieh, A., Curti, E., Lemmens, K., Vandenborre, J., de Pablo, J., Casas, I., Clarens, F., Hózer, Z., Roth, O. & Mennecart, T. (Peer reviewer), Dec 2014, Conference Proceedings EURADWASTE ’13. Spain, Vol. 1. p. 221-228

  Research output › peer-review

• 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, Vol. 1475. p. 119-124 6 p. (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. (Peer reviewer), 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. (Peer reviewer), 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. (Peer reviewer), Dec 2012, MRS Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXXV. United States, Vol. 1475. p. 131-136 6 p. (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

• UO₂ dissolution in high pH conditions of the Belgian Supercontainer

  Mennecart, T., Cachoir, C. & Lemmens, K., 2012, Scientific Basis for Nuclear Waste Management XXXV. Vol. 1475. p. 293-298 6 p. (Materials Research Society Symposium Proceedings; vol. 1475).

  Research output › peer-review
  4 Scopus citations
• 2011

  Estimation of the effective surface area of UOX (MOX) spent fuel in Supercontainer disposal conditions (status 2010)

  Cachoir, C. & Mennecart, T., Feb 2011, 0 ed. SCK CEN. 32 p. (SCK•CEN Reports; no. ER-142)

  Research output › peer-review

• The effect of cement on the UO2 dissolution rate and UO2 solubility , Programme 2004-2008, status March 2009

  Mennecart, T., Cachoir, C. & Lemmens, K., Feb 2011, 0 ed. SCK CEN. 124 p. (SCK CEN Reports; no. ER-156)

  Research output › peer-review

  Open Access

  File
• 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., 2009, Scientific Basis for Nuclear Waste Management XXXIII: Symposium Proceedings. Warrendale, PA, United States: MRS - Materials Research Society, Vol. 1193. p. 597-604 8 p. (Materials Research Society Symposium Proceedings; vol. 1193).

  Research output › peer-review

  Open Access
• 2007

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

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

  Research output › peer-review

• 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., 2007, Proceedings of the ICEM2007: 11th International Conference on Environmental Remediation and Radioactive Waste Management. PART B ed. Fairfield, NJ, United States, p. 845-852 8 p. (Proceedings of the ICEM2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management; no. PART B).

  Research output › peer-review

  Open Access