Journal of Nuclear Materials

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The measurement of silver diffusivity in zirconium carbide to study the release behavior of 110mAg in the ZrC TRISO-coated nuclear fuel particle
Journal of Nuclear Materials - Tập 470 - Trang 76-83 - 2016
Young-Ki Yang, Todd R. Allen
Investigation of the compatibility of tungsten and high temperature sodium
Journal of Nuclear Materials - Tập 343 - Trang 360-365 - 2005
Yong-Li Xu, Bin Long, Yuan-Chao Xu, Hua-Qing Li
Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER
Journal of Nuclear Materials - Tập 463 - Trang 11-21 - 2015
S. Brezinsek
An electron microscope study of the thermal oxidation of natural graphite
Journal of Nuclear Materials - Tập 10 - Trang 99-112 - 1963
A.E.B. Presland, J.A. Hedley
Oxidation of U-10 at% Zr alloy in air at 432–1028 K
Journal of Nuclear Materials - Tập 210 Số 1-2 - Trang 172-177 - 1994
A time dependent model to study the effect of surface roughness on reactive–diffusive transport in porous media
Journal of Nuclear Materials - Tập 390 - Trang 203-206 - 2009
M. Warrier, A. Rai, R. Schneider
Laser-fusion reactor materials problems resulting from fusion microexplosion emissions
Journal of Nuclear Materials - Tập 63 - Trang 31-36 - 1976
T.G. Frank, L.A. Booth
Performance of oxide nuclear fuel in water-cooled power reactors
Journal of Nuclear Materials - Tập 153 - Trang 3-15 - 1988
H. Stehle
Preparation of porous magnesium oxide foam and study on its enrichment of uranium
Journal of Nuclear Materials - Tập 504 - Trang 166-175 - 2018
Yunsheng Wang, Yuantao Chen, Chen Liu, Fang Yu
The effect of fission fragment irradiation upon the active to passive transition in the oxidation of self-bonded refel silicon carbide at 850–950°C
Journal of Nuclear Materials - Tập 52 - Trang 184-190 - 1974
M.J. Bennett, G.H. Chaffey
Tổng số: 13,429   
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