Search Results - "Pouchon, M.A."

Ion irradiation enhances the mechanical performance of metallic glasses by Raghavan, R., Boopathy, K., Ghisleni, R., Pouchon, M.A., Ramamurty, U., Michler, J.

“…We demonstrate that irradiation may enhance the plasticity in metallic glasses by increasing the free-volume content via micropillar compression experiments on…”
Get full text

Fabrication of CeO2 ceramic spheres as a surrogate of nuclear fuel by an improved microwave-assisted rapid internal gelation process by Tian, Wei, Pouchon, M.A., Guo, Hangxu, Chen, Denglei, Yin, Xiaojie, Qin, Zhi

“…CeO2 is a surrogate of PuO2 in nuclear fuel development. Uniform sized ceramic CeO2 spheres were fabricated by an improved internal gelation process which…”
Get full text

Preparation of UC ceramic nuclear fuel microspheres by combination of an improved microwave-assisted rapid internal gelation with carbothermic reduction process by Tian, Wei, Guo, Hangxu, Chen, Desheng, Pouchon, M.A., Horwege, Alina, Yin, Xiaojie, Huang, Qinggang, Wang, Jieru, Cao, Shiwei, Chen, Denglei, Bai, Jing, Tan, Cunmin, Fan, Fangli, Wu, Xiaolei, Shen, Tielong, Qin, Zhi

“…Uranium carbide (UC) ceramic microspheres filled into a cladding are a potential nuclear fuel format for nuclear reactors. Uniform sized ceramic UC…”
Get full text

A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment by Balbaud, F., Cabet, C., Cornet, S., Dai, Y., Gan, J., Hernández Mayoral, M., Hernández, R., Jianu, A., Malerba, L., Maloy, S.A., Marrow, J., Ohtsuka, S., Okubo, N., Pouchon, M.A., Puype, A., Stergar, E., Serrano, M., Terentyev, D., Wang, Y.G., Weisenburger, A.

“…•A TRL scale was proposed for innovative material solutions for nuclear applications.•More than 40 activities, national or international projects have been…”
Get full text

Irradiation creep and microstructural changes in an advanced ODS ferritic steel during helium implantation under stress by Chen, J., Pouchon, M.A., Kimura, A., Jung, P., Hoffelner, W.

“…An advanced oxide dispersion strengthened (ODS) ferritic steel with very fine oxide particles has been homogeneously implanted with helium under uniaxial…”
Get full text

An X-ray absorption spectroscopy study of an oxide dispersion strengthened steel by Pouchon, M.A., Kropf, A.J., Froideval, A., Degueldre, C., Hoffelner, W.

“…Oxide dispersion strengthened (ODS) steels are being investigated as possible structural material for components of future nuclear power plants. The…”
Get full text

Niobium speciation at the metal/oxide interface of corroded niobium-doped Zircaloys: A X-ray absorption near-edge structure study by Froideval, A., Degueldre, C., Segre, C.U., Pouchon, M.A., Grolimund, D.

“…X-ray absorption near-edge structure (XANES) spectroscopy is applied to Zr-based alloys ((Zr, x%Nb) with x ⩽ 1 wt.%) corroded in steam at 415 °C to resolve the…”
Get full text

Macro and microscale mechanical testing and local electrode atom probe measurements of STIP irradiated F82H, Fe–8Cr ODS and Fe–8Cr–2W ODS by Hosemann, P., Stergar, E., Peng, L., Dai, Y., Maloy, S.A., Pouchon, M.A., Shiba, K., Hamaguchi, D., Leitner, H.

“…The reduced activation ferritic/martensitic alloy F82H (Fe–8Cr–2W–0.2V–0.04Ta–0.1C) is being considered as a structural material for several different fusion…”
Get full text

Irradiation creep and precipitation in a ferritic ODS steel under helium implantation by Chen, J., Jung, P., Pouchon, M.A., Rebac, T., Hoffelner, W.

“…Ferritic oxide dispersion strengthened (ODS) steel, PM2000, has been homogeneously implanted with helium under uniaxial tensile stresses from 20 to 250 MPa to…”
Get full text

Innovative production of nuclear fuel by microwave internal gelation: Heat transfer model of falling droplets by Cabanes-Sempere, M., Cozzo, C., Vaucher, S., Catalá-Civera, J.M., Pouchon, M.A.

“…Based on closed packed microspheres produced by internal gelation, the Sphere-pac concept provides a safer and cleaner process and better remote production…”
Get full text

Nuclear material investigations by advanced analytical techniques by Degueldre, C., Kuri, G., Martin, M., Froideval, A., Cammelli, S., Orlov, A., Bertsch, J., Pouchon, M.A.

“…Advanced analytical techniques have been used to characterize nuclear materials at the Paul Scherrer Institute during the last decade. The analysed materials…”
Get full text

Oxide dispersion strengthened steel irradiation with helium ions by Pouchon, M.A., Chen, J., Döbeli, M., Hoffelner, W.

“…Oxide dispersion strengthened (ODS) ferritic steels are investigated as possible structural material for the future generation of high temperature gas cooled…”
Get full text

Manufacturing of zirconia microspheres doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel by Idemitsu, K., Arima, T., Inagaki, Y., Torikai, S., Pouchon, M.A.

“…Zirconium oxide is an inert matrix candidate for the transmutation of plutonium in light water reactor (LWR). The thermal conductivity of cubic zirconia is…”
Get full text

Cermet sphere-pac concept for inert matrix fuel by Pouchon, M.A., Nakamura, M., Hellwig, Ch, Ingold, F., Degueldre, C.

“…In the inert matrix fuel concept, plutonium reprocessed from spent fuel is burned in an inert matrix, e.g. yttria-stabilized zirconia. Coming from wet…”
Get full text

Characterization of free falling drops inside a microwave cavity by Cabanes-Sempere, M., Cozzo, C., Catala-Civera, J.M., Penaranda-Foix, F.L., Ishizaki, K., Vaucher, S., Pouchon, M.A.

“…Microwave Internal Gelation (MIG) is a chemical process proposed for the production of nuclear particle fuel. The reaction is triggered by a temperature…”
Get full text

Inert matrix fuel for the utilisation of plutonium by Ledergerber, G., Degueldre, C., Heimgartner, P., Pouchon, M.A., Kasemeyer, U.

“…Utilising fuel resources responsibly, reducing waste volume and emissions as well as conflict potentials within the international community (non-proliferation,…”
Get full text

Behavior of cesium implanted in zirconia based inert matrix fuel by Pouchon, M.A., Döbeli, M., Degueldre, C., Burghartz, M.

“…Retention of cesium in yttria stabilized zirconia (YSZ) was studied experimentally and discussed on the basis of its solubility estimated on a thermodynamic…”
Get full text

Determination of the thermal conductivity in zirconia based inert matrix nuclear fuel by oscillating differential scanning calorimetry and laser flash by Pouchon, M.A., Degueldre, C., Tissot, P.

“…The performances of oscillating differential scanning calorimetry (ODSC) and laser-flash technique in determining the thermal conductivity and the specific…”
Get full text

The influence of carbonate complexes on the solubility of zirconia: new experimental data by Pouchon, M.A., Curti, E., Degueldre, C., Tobler, L.

“…New experiments conducted at pH 9 and 298 K clearly indicate that addition of bicarbonate ions in aqueous solutions increases the solubility of both cubic and…”
Get full text

Retention of iodine in yttria stabilized zirconia by Pouchon, M.A, Döbeli, M, Degueldre, C

“…The diffusion behavior of iodine in yttria stabilized zirconia (YSZ) was investigated as a function of the temperature. Iodine implantation was performed in…”
Get full text