Volume 460

Journal of Nuclear Materials

Volume 460

1

Radiation damage resistance and interface stability of copper–graphene nanolayered composite

Huang, Hai, Tang, Xiaobin, Chen, Feida, Yang, Yahui, Liu, Jian, Li, Huan, Chen, Da

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.56 MB

english, 2015

2

The corrosion product of Cs–Te corrosive compound with 11Cr-Ferritic/Martensitic Steel and 9Cr-Oxide Dispersion Strengthened steel

Sasaki, K., Tanigaki, T., Fujimura, R., Fukumoto, K., Uno, M.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.77 MB

english, 2015

3

Diffusion of point defects, nucleation of dislocation loops, and effect of hydrogen in hcp-Zr: Ab initio and classical simulations

Christensen, M., Wolf, W., Freeman, C., Wimmer, E., Adamson, R.B., Hallstadius, L., Cantonwine, P.E., Mader, E.V.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 4.06 MB

english, 2015

4

Measurement of cesium diffusion coefficients in graphite IG-110

Carter, L.M., Brockman, J.D., Loyalka, S.K., Robertson, J.D.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1009 KB

english, 2015

5

Thermodynamic assessment of the U–Y–O system

Brese, R.G., McMurray, J.W., Shin, D., Besmann, T.M.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.57 MB

english, 2015

6

Internal stresses at the crystalline scale in textured ZrO2 films before lateral cracking

Berdin, Clotilde, Pascal, Serge, Tang, Yan

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.21 MB

english, 2015

7

Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures

Silva, Chinthaka M., Katoh, Yutai, Voit, Stewart L., Snead, Lance L.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 4.41 MB

english, 2015

8

Interaction of 〈100〉 dislocation loops with dislocations studied by dislocation dynamics in α-iron

Shi, X.J., Dupuy, L., Devincre, B., Terentyev, D., Vincent, L.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 986 KB

english, 2015

9

Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor

Renault Laborne, Alexandra, Gavoille, Pierre, Malaplate, Joël, Pokor, Cédric, Tanguy, Benoît

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.92 MB

english, 2015

10

Delayed hydride crack growth study on irradiated Zr–2.5Nb pressure tube

Shah, Priti Kotak, Dubey, J.S., Kumar, Ashwini, Shriwastaw, R.S., Rath, B.N., Pandit, K.M., Dhotre, M.P., Mishra, P., Alur, V.D., Anantharaman, S.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.48 MB

english, 2015

11

Associations of Pd, U and Ag in the SiC layer of neutron-irradiated TRISO fuel

Lillo, T.M., van Rooyen, I.J.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 3.32 MB

english, 2015

12

Zr inclusions in actinide–Zr alloys: New data and ideas about how they form

Janney, Dawn E., O’Holleran, Thomas P.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 576 KB

english, 2015

13

Interaction of dislocations with carbides in BCC Fe studied by molecular dynamics

Granberg, F., Terentyev, D., Nordlund, K.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.09 MB

english, 2015

14

Simulation of neutron-induced damage in tungsten by irradiation with energetic self-ions

Ogorodnikova, O.V., Gann, V.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 905 KB

english, 2015

15

A first-principles study of He, Xe, Kr and O incorporation in thorium carbide

Pérez Daroca, D., Llois, A.M., Mosca, H.O.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.15 MB

english, 2015

16

Effects of heat treatment on U–Mo fuel foils with a zirconium diffusion barrier

Jue, Jan-Fong, Trowbridge, Tammy L., Breckenridge, Cynthia R., Moore, Glenn A., Meyer, Mitchell K., Keiser, Dennis D.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 4.20 MB

english, 2015

17

Comparative study of helium effects on EU-ODS EUROFER and EUROFER97 by nanoindentation and TEM

Roldán, M., Fernández, P., Rams, J., Jiménez-Rey, D., Materna-Morris, E., Klimenkov, M.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 3.38 MB

english, 2015

18

Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels

Gussev, Maxim N., Field, Kevin G., Busby, Jeremy T.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 4.40 MB

english, 2015

19

Low temperature decomposition of U(IV) and Th(IV) oxalates to nanograined oxide powders

Tyrpekl, Vaclav, Vigier, Jean-Francois, Manara, Dario, Wiss, Thierry, Dieste Blanco, Oliver, Somers, Joseph

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.37 MB

english, 2015

20

Experimental characterization and modeling of UO2 grain boundary cracking at high temperatures and high strain rates

Salvo, Maxime, Sercombe, Jérôme, Helfer, Thomas, Sornay, Philippe, Désoyer, Thierry

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 3.32 MB

english, 2015

21

Reactivity of Zircaloy-4 with Ti3SiC2 and Ti2AlC in the 1100–1300°C temperature range

Tallman, Darin J., Yang, Jian, Pan, Limei, Anasori, Babak, Barsoum, Michel W.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.78 MB

english, 2015

22

High temperature steam oxidation of SiC coating layer of TRISO fuel particles

Terrani, Kurt A., Silva, Chinthaka M.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.82 MB

english, 2015

23

Crack growth rate in core shroud horizontal welds using two models for a BWR

Arganis Juárez, C.R., Hernández Callejas, R., Medina Almazán, A.L.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 987 KB

english, 2015

24

Editorial board

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 34 KB

english, 2015

25

Identification and location of 14C-bearing species in thermally treated neutron irradiated graphites NBG-18 and NBG-25: Pre- and post-thermal treatment

LaBrier, Daniel, Dunzik-Gougar, Mary Lou

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.74 MB

english, 2015

26

Assessing the oxygen stoichiometry during the sintering of (U, Pu)O2 fuel

Vaudez, Stéphane, Léchelle, Jacques, Berzati, Ségolène, Heintz, Jean-Marc

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.59 MB

english, 2015

27

Fast, quantitative, and nondestructive evaluation of hydrided LWR fuel cladding by small angle incoherent neutron scattering of hydrogen

Yan, Y., Qian, S., Littrell, K., Parish, C.M., Plummer, L.K.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 2.87 MB

english, 2015

28

Aging of magnesium stearate under high doses gamma irradiation and oxidative conditions

Lebeau, D., Beuvier, L., Cornaton, M., Miserque, F., Tabarant, M., Esnouf, S., Ferry, M.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1.38 MB

english, 2015

29

XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)

Dardenne, K., González-Robles, E., Rothe, J., Müller, N., Christill, G., Lemmer, D., Praetorius, R., Kienzler, B., Metz, V., Roth, G., Geckeis, H.

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 1013 KB

english, 2015