-
1
-
-
0037202273
-
The uranium ore from Mina Fe (Salamanca, Spain) as a natural analogue of processes in a Used Fuel repository
-
Pérez del Villar L., Bruno J., Campos R., Gómez P., Cózar J.S., Garralón A., et al., The uranium ore from Mina Fe (Salamanca, Spain) as a natural analogue of processes in a Used Fuel repository, Chem. Geol., 2002, 190, 395-415
-
(2002)
Chem. Geol.
, vol.190
, pp. 395-415
-
-
Pérez Del, V.L.1
Bruno, J.2
Campos, R.3
Gómez, P.4
Cózar, J.S.5
Garralón, A.6
-
2
-
-
0034324911
-
Fuel corrosion processes under waste disposal conditions
-
Shoesmith D.W., Fuel corrosion processes under waste disposal conditions, J. Nucl. Mater., 2000, 282, 1-31
-
(2000)
J. Nucl. Mater.
, vol.282
, pp. 1-31
-
-
Shoesmith, D.W.1
-
3
-
-
0036378695
-
The influence of near-field redox conditions on Spent Fuel leaching
-
Spahiu K., Eklund U.-B., Cui D., and Lundström M., The influence of near-field redox conditions on Spent Fuel leaching, Mater. Res. Soc. Symp. P., 2002, 713, 633-638
-
(2002)
Mater. Res. Soc. Symp. P.
, vol.713
, pp. 633-638
-
-
Spahiu, K.1
Eklund, U.-B.2
Cui, D.3
Lundström, M.4
-
4
-
-
26444538482
-
The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2
-
Stroes-Gascoyne S., Garisto F., and Betteridge J.S., The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2, J. Nucl. Mater., 2005, 346, 5-15
-
(2005)
J. Nucl. Mater.
, vol.346
, pp. 5-15
-
-
Stroes-Gascoyne, S.1
Garisto, F.2
Betteridge, J.S.3
-
5
-
-
0242393927
-
Observation of studtite and metastudtite on spent fuel
-
McNamara B., Buck E.C., and Hanson B., Observation of studtite and metastudtite on spent fuel, Mater. Res. Soc. Symp. P., 2003, 757, 401-406
-
(2003)
Mater. Res. Soc. Symp. P.
, vol.757
, pp. 401-406
-
-
McNamara, B.1
Buck, E.C.2
Hanson, B.3
-
6
-
-
84858039286
-
Nuclear fuel in a reactor accident
-
Burns P.C., Ewing R.C., Navrotsky A., Nuclear fuel in a reactor accident, Science, 2012, 335, 1184-1188
-
(2012)
Science
, vol.335
, pp. 1184-1188
-
-
Burns, P.C.1
Ewing, R.C.2
Navrotsky, A.3
-
7
-
-
0242582184
-
Stability of peroxide-containing uranyl minerals
-
Hughes-Kubatko K.-A., Helean K.B., Navrotsky A., and Burns P.C., Stability of peroxide-containing uranyl minerals, Science, 2003, 302, 1191-1193
-
(2003)
Science
, vol.302
, pp. 1191-1193
-
-
Hughes-Kubatko, K.-A.1
Helean, K.B.2
Navrotsky, A.3
Burns, P.C.4
-
8
-
-
0032072373
-
Calculation of radiation dose rates in a water layer in contact with used CANDU UO2 fuel
-
Sunder S., Calculation of radiation dose rates in a water layer in contact with used CANDU UO2 fuel, Nuclear Technology, 1998, 122, 211-221
-
(1998)
Nuclear Technology
, vol.122
, pp. 211-221
-
-
Sunder, S.1
-
9
-
-
84866389502
-
Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel
-
Metz V., Geckeis H., Gonzalez-Robles E., Loida A., Bube C., and Kienzler B., Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel, Radiochim. Acta, 2012, 100, 699-713
-
(2012)
Radiochim. Acta
, vol.100
, pp. 699-713
-
-
Metz, V.1
Geckeis, H.2
Gonzalez-Robles, E.3
Loida, A.4
Bube, C.5
Kienzler, B.6
-
10
-
-
34248644595
-
Spent nuclear fuel
-
Bruno J. and Ewing R.C., Spent Nuclear Fuel, Elements, 2006, 2, 343-349
-
(2006)
Elements
, vol.2
, pp. 343-349
-
-
Bruno, J.1
Ewing, R.C.2
-
11
-
-
84989899796
-
MCNPX user's manual version 2.6.0, Los Alamos national laboratory
-
LA-CP-07-1473
-
Pelowitz D.B., MCNPX User's Manual Version 2.6.0, Los Alamos National Laboratory, Tech. Rep. LA-CP-07-1473, 2008
-
(2008)
Tech. Rep.
-
-
Pelowitz, D.B.1
-
13
-
-
84989861582
-
-
Karlsruhe Institute of Technology (KIT), Karlsruhe KIT-SR 7639
-
Kienzler B., Metz V., Duro L., and Valls E.A., 1st Annual Workshop Proceedings of the Collaborative Project ?FIRST-Nuclides', Karlsruhe Institute of Technology (KIT), Karlsruhe KIT-SR 7639, 2013
-
(2013)
1st Annual Workshop Proceedings of the Collaborative Project? FIRST-Nuclides
-
-
Kienzler, B.1
Metz, V.2
Duro, L.3
Valls, E.A.4
-
14
-
-
84989882189
-
-
Institute for Nuclear Waste Disposal, H. Geckeis, T. Stumpf
-
Bohnert E., Bube C., Janata E., Kelm M., Kienzler B., Metz V. et al., In KIT SCIENTIFIC REPORTS 7559 - Annual Report 2009, Institute for Nuclear Waste Disposal, H. Geckeis, T. Stumpf (eds.), 2010, 36-40, ISSN 1869-9669
-
(2009)
KIT SCIENTIFIC REPORTS 7559 - Annual Report
, vol.2010
, pp. 36-40
-
-
Bohnert, E.1
Bube, C.2
Janata, E.3
Kelm, M.4
Kienzler, B.5
Metz, V.6
-
15
-
-
84885187884
-
Dynamic leaching studies of48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions
-
Serrano-Purroy D., Casas I., González-Robles E., Glatz J.P., Wegen D.H., Clarens F., et al., Dynamic leaching studies of48 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions; J. Nucl. Mater., 2013, 434(1-3), 451-460
-
(2013)
J. Nucl. Mater.
, vol.434
, Issue.1-3
, pp. 451-460
-
-
Serrano-Purroy, D.1
Casas, I.2
González-Robles, E.3
Glatz, J.P.4
Wegen, D.H.5
Clarens, F.6
-
16
-
-
0030218638
-
Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40-67 GWd/tM
-
Spino J., Vennix K., and Coquerelle M., Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40-67 GWd/tM, J. Nucl. Mater., 1996, 231(3), 179-190
-
(1996)
J. Nucl. Mater.
, vol.231
, Issue.3
, pp. 179-190
-
-
Spino, J.1
Vennix, K.2
Coquerelle, M.3
-
17
-
-
84944684986
-
-
webKorigen, Nucleonica GmbH
-
webKorigen, Nucleonica GmbH, Nucleonica Nuclear Science Portal, 2011, www.nucleonica.com
-
(2011)
Nucleonica Nuclear Science Portal
-
-
-
19
-
-
84989893999
-
-
Institut für Strahlenforschung, J. U. Knebel U. Mohr (eds.), Simulationen zur α-Dosisleistung in einer Wasserschicht an der Oberfläche eines Kernbrennstoff-Pellets ISSN 1869-9669 (in German)
-
Becker F., Zimmermann Ch., Poyo-Terrero M., Zhang G., and Kienzler B., In KIT SCIENTIFIC REPORTS 7587 - Jahresbericht 2010, Institut für Strahlenforschung, J. U. Knebel U. Mohr (eds.), Simulationen zur α-Dosisleistung in einer Wasserschicht an der Oberfläche eines Kernbrennstoff-Pellets, 2011, 28-31, ISSN 1869-9669 (in German)
-
(2011)
KIT SCIENTIFIC REPORTS 7587 - Jahresbericht 2010
, pp. 28-31
-
-
Becker, F.1
Ch, Z.2
Poyo-Terrero, M.3
Zhang, G.4
Kienzler, B.5
-
20
-
-
0008773421
-
-
Swedish Nuclear Fuel and Waste Management Co (SKB) TR
-
Werme L., Sellin P., and Forsyth R., Radiolytically induced oxidative dissolution of spent nuclear fuel, Swedish Nuclear Fuel and Waste Management Co (SKB), 1990, TR 90-08
-
(1990)
Radiolytically Induced Oxidative Dissolution of Spent Nuclear Fuel
, pp. 90-108
-
-
Werme, L.1
Sellin, P.2
Forsyth, R.3
-
21
-
-
67349144172
-
Corrosion of irradiated MOX fuel in presence of dissolved H2
-
Carbol P., Fors P., Van Winckel S., and Spahiu K., Corrosion of irradiated MOX fuel in presence of dissolved H2, J. Nucl. Mater., 2009, 392, 45-54
-
(2009)
J. Nucl. Mater.
, vol.392
, pp. 45-54
-
-
Carbol, P.1
Fors, P.2
Van Winckel, S.3
Spahiu, K.4
-
22
-
-
33746368836
-
The relative impact of radiolysis products in radiation induced oxidative dissolution of UO2
-
Ekeroth E., Roth O., and Jonsson M., The relative impact of radiolysis products in radiation induced oxidative dissolution of UO2, J. Nucl. Mater., 2006, 355, 38-4
-
(2006)
J. Nucl. Mater.
, vol.355
, pp. 38-134
-
-
Ekeroth, E.1
Roth, O.2
Jonsson, M.3
-
23
-
-
15944416737
-
Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix
-
Jégou C., Muzeau B., Broudic V., Peuget S., Poulesquen A., Roudil D., et al., Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix, J. Nucl. Mater., 2005, 341, 62-82
-
(2005)
J. Nucl. Mater.
, vol.341
, pp. 62-82
-
-
Jégou, C.1
Muzeau, B.2
Broudic, V.3
Peuget, S.4
Poulesquen, A.5
Roudil, D.6
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