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Journal of nuclear materials

Total activitats: 41
Títol addicional
ScienceDirect e-journals
ISSN
0022-3115 Obrir en finestra nova
Publicació / Producció
New York, NY : Elsevier Science Pub. Co., [199?]-
Editorial
Elsevier
URL
https://www.sciencedirect.com/science/journal/00223115 Obrir en finestra nova

Producció científica

1 a 41 de 41 resultats
 
  • Edge dislocations as sinks for sub-nanometric radiation induced defects in a-iron

     Anento, N.; Malerba, L.; Serra, A.
    Journal of nuclear materials
    Vol. 498, p. 341-347
    DOI: 10.1016/j.jnucmat.2017.10.053
    Data de publicació: 2018-01
    Article en revista
  • Instant release fraction corrosion studies of commercial UO2 BWR spent nuclear fuel  Accés obert

     Martinez, A.; Serrano-Purroy, D.; Sureda, R.; Casas, I.; De Pablo, J.
    Journal of nuclear materials
    Vol. 488, p. 302-313
    DOI: 10.1016/j.jnucmat.2017.03.022
    Data de publicació: 2017-05-01
    Article en revista
    Accés al text complet
  • UO2 surface oxidation by mixtures of water vapor and hydrogen as a function of temperature

     Espriu-Gascon, A.; Llorca, J.; Dominguez, M.; Gimenez, F.; Casas, I.; De Pablo, J.
    Journal of nuclear materials
    Vol. 467, p. 240-243
    DOI: 10.1016/j.jnucmat.2015.09.047
    Data de publicació: 2015-12-01
    Article en revista
  • Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction  Accés obert

     Gonzalez, E.; Serrano, D.; Sureda, R.; Casas, I.; De Pablo, J.
    Journal of nuclear materials
    Vol. 465, p. 63-70
    DOI: 10.1016/j.jnucmat.2015.05.012
    Data de publicació: 2015-10-01
    Article en revista
    Accés al text complet
  • Interaction of He and He-V clusters with self-interstitials and dislocations defects in bcc Fe  Accés obert

     Terentyev, D.; Anento, N.; Serra, A.; Ortiz, C.; zhurkin , E.
    Journal of nuclear materials
    Vol. 458, p. 11-21
    DOI: 10.1016/j.jnucmat.2014.10.093
    Data de publicació: 2015-03-01
    Article en revista
    Accés al text complet
  • Carbon-vacancy complexes as traps for self-interstitial clusters in Fe-C alloys

     Anento, N.; Serra, A.
    Journal of nuclear materials
    Vol. 440, num. 1-3, p. 236-242
    DOI: 10.1016/j.jnucmat.2013.04.087
    Data de publicació: 2013-09-01
    Article en revista
  • Dynamic leaching studies of 48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions

     Serrano, D.; Casas, I.; Gonzalez, E.; Glatz, J.P.; Wegen, D.; Clarens Blanco, F.; Gimenez, F.; De Pablo, J.; Martinez-Esparza, A.
    Journal of nuclear materials
    Vol. 434, num. 1-3, p. 451-460
    DOI: 10.1016/j.jnucmat.2011.03.020
    Data de publicació: 2013-03
    Article en revista
  • Osmosis-induced water uptake by Eurobitum bituminized radioactive waste and pressure development in constant volume conditions

     Mariën, A.; Mokni, N.; Valcke, E.; Olivella, S.; Smets, E.; Li, X.L.
    Journal of nuclear materials
    Vol. 432, num. 1-3, p. 348-365
    DOI: 10.1016/j.jnucmat.2012.08.032
    Data de publicació: 2013-01
    Article en revista
  • Instant release fraction and matrix release of high burn-up UO2 spent nuclear fuel: Effect of high burn-up structure and leaching solution composition

     Serrano, D.; Clarens Blanco, F.; Gonzalez, E.; Glatz, J.P.; Wegen, D.; De Pablo, J.; Casas, I.; Gimenez, F.; Martinez-Esparza, A.
    Journal of nuclear materials
    Vol. 427, num. 1-3, p. 249-258
    DOI: 10.1016/j.jnucmat.2012.04.036
    Data de publicació: 2012-08
    Article en revista
  • Envisaging palladium chemical transport mechanism from fuel kernel pellet to SiC cladding by bromination

     Arias, F.J.
    Journal of nuclear materials
    Vol. 426, num. 1-3, p. 226-228
    DOI: 10.1016/j.jnucmat.2012.03.020
    Data de publicació: 2012-07
    Article en revista
  • Interaction of < 100 > loops with carbon atoms and < 100 > dislocations in BCC Fe: an atomistic study

     Terentyev, D.; Anento, N.; Serra, A.
    Journal of nuclear materials
    Vol. 420, num. 1-3, p. 9-15
    DOI: 10.1016/j.jnucmat.2011.08.037
    Data de publicació: 2012-01
    Article en revista
  • Interaction of carbon with vacancy and self-interstitial atom clusters in alpha-iron studied using metallic-covalent interatomic potential

     Terentyev, D.; Anento, N.; Serra, A.; Jansson, V.; Khater, H.A.; Bonny, G.
    Journal of nuclear materials
    Vol. 408, num. 3, p. 272-284
    DOI: 10.1016/j.jnucmat.2010.11.053
    Data de publicació: 2011-01-31
    Article en revista
  • Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules

     Fradera, J.; Sedano, L.; Mas de les Valls, E.; Batet, L.
    Journal of nuclear materials
    Vol. 417, num. 1-3, p. 739-742
    DOI: 10.1016/j.jnucmat.2011.02.008
    Data de publicació: 2011
    Article en revista
  • Comparison of empirical interatomic potentials for iron applied to radiation damage studies

     Malerba, L.; Marinica, M.; Anento, N.; Björkas, C.; Nguyen, H.; Domain, C.; Djurabekova, F.; Olsson, P.; Nordlund, K.; Serra, A.; Terentyev, D.; Willaime, F.; Becquart, C.
    Journal of nuclear materials
    Vol. 406, num. 1, p. 19-38
    DOI: 10.1016/j.jnucmat.2010.05.017
    Data de publicació: 2010-11-01
    Article en revista
  • Osmosis-induced swelling of Eurobitum bituminized radioactive waste in constant total stress conditions

     Valcke, E.; Mariën, A.; Smets, E.; Mokni, N.; Olivella, S.; Sillen, X.
    Journal of nuclear materials
    Vol. 406, num. 3, p. 304-316
    DOI: 10.1016/j.jnucmat.2010.08.060
    Data de publicació: 2010-11
    Article en revista
  • Deformation of bitumen based porous material: experimental and numerical analysis

     Mokni, N.; Olivella, S.; Li, X.L.; Smets, E.; Valcke, E.; Mariën, A.
    Journal of nuclear materials
    Vol. 404, num. 2, p. 144-153
    DOI: 10.1016/j.jnucmat.2010.07.019
    Data de publicació: 2010-09
    Article en revista
  • Thorium sorption onto magnetite and ferrihydrite in acidic conditions

     Rojo, I.; Seco, F.; Rovira, M.; Giménez, J.; Cervantes, G.; Martí, V.; De Pablo, J.
    Journal of nuclear materials
    Vol. 385, num. 2, p. 474-478
    Data de publicació: 2009-03
    Article en revista
  • Effect of temperature on studtite stability: Thermogravimetry and differential scanning calorimetry investigations

     Rey, A.; Casas, I.; Gimenez, F.; Quiñones Ruiz, Jose Miguel; De Pablo, J.
    Journal of nuclear materials
    Vol. 385, num. 2, p. 467-473
    Data de publicació: 2009-03
    Article en revista
  • Thorium sorption onto magnetite and ferrihydrate in acidic conditions

     Rojo, I.; Seco, F.; Rovira, M.; Gimenez, F.; Cervantes, G.; Martí, V.; De Pablo, J.
    Journal of nuclear materials
    Vol. 385, num. 2, p. 474-478
    DOI: 10.1016/j.jnucmat.2008.12.014
    Data de publicació: 2009-01-01
    Article en revista
  • Lead-lithium eutectic material database for nuclear fusion technology

     Mas de les Valls, E.; Sedano, L.; Batet, L.; Ricapito, I.; Aiello, A.; Gastaldi, O.; Gabriel, F.
    Journal of nuclear materials
    Vol. 376, num. 3, p. 353-357
    Data de publicació: 2008-09
    Article en revista
  • Spent fuel canister for geological repository: Inner material requirements and candidates evaluation

     Puig, F.; Dies, J.; De Pablo, J.; Martinez-Esparza, A.
    Journal of nuclear materials
    Vol. 376, num. 2, p. 181-191
    Data de publicació: 2008-05
    Article en revista
  • Determination of UO2(s) dissolution rates in a hydrogen peroxide medium as a function of pressure and temperature

     Casas, I.; Borrell, M.; Sanchez, L.; De Pablo, J.; Gimenez, F.; Clarens Blanco, F.
    Journal of nuclear materials
    Vol. 375, num. 1, p. 151-156
    Data de publicació: 2008-03
    Article en revista
  • Interaction of a single interstitial atom with small clusters of self interstitials in alpha-Fe

     Anento, N.; Serra, A.
    Journal of nuclear materials
    Vol. 372, num. 2-3, p. 239-248
    DOI: 10.1016/j.jnucmat.2007.03.230
    Data de publicació: 2008-01
    Article en revista
  • Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments

     Merino, J.; CERA, E.; Bruno, J.; Quiñones Ruiz, Jose Miguel; Casas, I.; Clarens Blanco, F.; Gimenez, F.; De Pablo, J.; Rovira, M.; Martinez-Esparza, A.
    Journal of nuclear materials
    Vol. 346, p. 40-47
    Data de publicació: 2005-11
    Article en revista
  • The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a fucntion of pH

     Clarens Blanco, F.; De Pablo, J.; Casas, I.; Gimenez, F.; Rovira, M.; Merino, J.; CERA, E.; Bruno, J.; Quiñones Ruiz, Jose Miguel; Martinez-Esparza, A.
    Journal of nuclear materials
    Vol. 345, p. 225-231
    Data de publicació: 2005-10
    Article en revista
  • Oxidation and dissolution of UO2 in bicarbonate media: Implications for the spent fuel oxidative dissolution mechanism

     Gimenez, F.; Clarens Blanco, F.; Casas, I.; Rovira, M.; De Pablo, J.; Bruno, J.
    Journal of nuclear materials
    Vol. 345, p. 232-238
    Data de publicació: 2005-10
    Article en revista
  • Study of loop-loop and loop-edge dislocation interactions in BCC iron

     Osetsky, Y.; Bacon, D.; Gao, F.; Serra, A.; Singh, B.
    Journal of nuclear materials
    Vol. 283-287, p. 784-788
    DOI: 10.1016/S0022-3115(00)00134-3
    Data de publicació: 2000-02
    Article en revista
  • On the validity of the cluster model to describe the evolution of CU precipitates in FE-CU alloys

     Golubov, S.; Serra, A.; Osetsky, Y.; Barashev, A.
    Journal of nuclear materials
    Vol. 277, p. 113-115
    DOI: 10.1016/S0022-3115(99)00238-X
    Data de publicació: 2000-01-02
    Article en revista
  • Interaction between interstitial clusters in Fe and Cu

     Osetsky, Y.; Serra, A.; Priego, V.
    Journal of nuclear materials
    Vol. 276, num. 1-3, p. 202-212
    DOI: 10.1016/S0022-3115(99)00179-8
    Data de publicació: 2000-01-01
    Article en revista
  • Stability and mobility of vacancy and interstitial clusters in BCC and FCC

     Osetsky, Y.; Bacon, D.; Serra, A.; Singh, B.; Golubov, S.
    Journal of nuclear materials
    Vol. 276, num. 1-3, p. 65-77
    DOI: 10.1016/S0022-3115(99)00170-1
    Data de publicació: 2000-01-01
    Article en revista
  • Interactions between mobile dislocation loops in Cu and a-Fe

     Osetsky, Y.; Serra, A.; Priego, V.
    Journal of nuclear materials
    Vol. 276, num. 1-3, p. 202-212
    DOI: 10.1016/S0022-3115(99)00179-8
    Data de publicació: 2000-01-01
    Article en revista
  • Stability and mobility of defect clusters and dislocation loops in metals

     Osetsky, Y.; Bacon, D.; Serra, A.; Singh, B.
    Journal of nuclear materials
    Vol. 276, num. 1-3, p. 65-77
    DOI: 10.1016/S0022-3115(99)00170-1
    Data de publicació: 2000-01-01
    Article en revista
  • Computer simulation of vacancy and interstitial clusters in BCC and FCC metals

     Osetsky, Y.; Victoria, M.; Serra, A.; Golubov, S.; Priego, V.
    Journal of nuclear materials
    Vol. 251, p. 34-48
    DOI: 10.1016/S0022-3115(97)00255-9
    Data de publicació: 1997-11
    Article en revista
  • Aspects of microstructure evolution under cascade damase conditions

     Singh, B.; Golubov, S.; Trinkaus, H.; Serra, A.; Osetsky, Y.; Barashev, A.
    Journal of nuclear materials
    Vol. 251, p. 107-122
    DOI: 10.1016/S0022-3115(97)00244-4
    Data de publicació: 1997-11
    Article en revista
  • Effect of H2O2, NaClO and Fe on the dissolution of unirradiated UO2 in NaCl5 mol kg-1. Comparision with spent fuel dissolution experiments

     Gimenez, F.; Baraj, E.; Torrero, M.; Casas, I.; De Pablo, J.
    Journal of nuclear materials
    Vol. 238, num. 0, p. 64-69
    Data de publicació: 1996-12
    Article en revista
  • LIBRETTO 3: Modelling tritium extraction/permeation and evaluation of permeation barriers under irradiation

     Sedano, L.; Rainer, C.; Fütterer, M.; Roberto, M.; Ramon, V.; Dies, J.
    Journal of nuclear materials
    Vol. 1, num. 233-237, p. 1411-1415
    Data de publicació: 1996-09
    Article en revista
  • Solid surface evolution model to predict uranium release from unirradiated UO2 and nuclear spent fuel dissolution under oxidizing conditions

     De Pablo, J.; Casas, I.; Gimenez, F.; Martí, V.; Torrero, M.
    Journal of nuclear materials
    Vol. 232, p. 138-145
    Data de publicació: 1996-09
    Article en revista
  • The evolution of copper precipitates in binary Fe-Cu alloys during ageing and irradiation

     Golubov, S.; Osetsky, Y.; Serra, A.; Barashev, A.
    Journal of nuclear materials
    Vol. 226, num. 1-2, p. 252-255
    DOI: 10.1016/0022-3115(95)00088-7
    Data de publicació: 1995-10
    Article en revista
  • Computer simulation study of copper precipitates in alfa-iron

     Osetsky, Y.; Mikhin, A.; Serra, A.
    Journal of nuclear materials
    Vol. 212-2015, num. Part 1, p. 236-240
    DOI: 10.1016/0022-3115(94)90063-9
    Data de publicació: 1994-09
    Article en revista
  • Static and dinamic SIMFUEL dissolution studies under oxic conditions

     Bruno, J.; Casas, I.; Sandino, A.
    Journal of nuclear materials
    Vol. 190, p. 61-69
    Data de publicació: 1992-01
    Article en revista