Volume 327; Issue 1

Journal of Nuclear Materials

Volume 327; Issue 1

1

A new method to study hydriding processes from the inner surfaces of fuel claddings

J.L. Sacedón, M. Dı́az, J.S. Moya, B. Remartı́nez, J. Izquierdo

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 608 KB

english, 2004

2

Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up

Koji Maeda, Takeo Asaga

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 719 KB

english, 2004

3

Constituent redistribution in U–Pu–Zr fuel during irradiation

Yeon Soo Kim, G.L Hofman, S.L Hayes, Y.H Sohn

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 590 KB

english, 2004

4

Effects of natural aging on the tensile properties of water-quenched U–6%Nb alloy

A.J Sunwoo, D.S Hiromoto

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 931 KB

english, 2004

5

Estimation of stress corrosion cracking sensitivity of type 304 stainless steel by magnetic force microscope

Shigeru Takaya, Takayuki Suzuki, Yoshihiro Matsumoto, Kazuyuki Demachi, Mitsuru Uesaka

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 731 KB

english, 2004

6

Effect of burn-up on the thermal conductivity of uranium dioxide up to 100.000 MWd t−1

C. Ronchi, M. Sheindlin, D. Staicu, M. Kinoshita

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 976 KB

english, 2004

7

Vitrification of high chrome oxide nuclear waste in iron phosphate glasses

Wenhai Huang, Delbert E. Day, Chandra S. Ray, Cheol-Woon Kim, Andrea Mogus-Milankovic

Journal:

Journal of Nuclear Materials

Year:

2004

Language:

english

File:

PDF, 1.47 MB

english, 2004

8

Editorial board

Journal:

Journal of Nuclear Materials

Year:

2004

File:

PDF, 16 KB

2004