Volume 113; Issue 2-3

Journal of Nuclear Materials

Volume 113; Issue 2-3
1

Thermal conductivity of solid UO2: Critique and recommendation

Year:
1983
Language:
english
File:
PDF, 834 KB
english, 1983
3

High temperature ductility of irradiated ferritic and austenitic steels

Year:
1983
Language:
english
File:
PDF, 341 KB
english, 1983
4

Creep fracture processes in zircaloy

Year:
1983
Language:
english
File:
PDF, 599 KB
english, 1983
6

SAXS study of molybdenum irradiated with helium ions

Year:
1983
Language:
english
File:
PDF, 1.19 MB
english, 1983
7

Defect production in ion-irradiated aluminum

Year:
1983
Language:
english
File:
PDF, 723 KB
english, 1983
8

Void-assisted grain boundary migration in ion-irradiated austenitic stainless steels

Year:
1983
Language:
english
File:
PDF, 1.68 MB
english, 1983
9

Stress corrosion cracking of zircaloy by cadmium, iodine, and metal iodides

Year:
1983
Language:
english
File:
PDF, 1.91 MB
english, 1983
10

Surface damage in UO2 due to mechanical polishing and ion bombardment

Year:
1983
Language:
english
File:
PDF, 421 KB
english, 1983
11

Pore geometry and interfacial energy

Year:
1983
Language:
english
File:
PDF, 246 KB
english, 1983
12

‘Breakaway’ growth in annealed Zircaloy-2 at 353 K and 553 K

Year:
1983
Language:
english
File:
PDF, 396 KB
english, 1983
16

The fracture surface energy of (U0.8Pu0.2)O2

Year:
1983
Language:
english
File:
PDF, 275 KB
english, 1983
17

Subject index

Year:
1983
Language:
english
File:
PDF, 298 KB
english, 1983
23

Cavity nucleation during post-irradiation creep

Year:
1983
Language:
english
File:
PDF, 539 KB
english, 1983
24

Author index

Year:
1983
Language:
english
File:
PDF, 146 KB
english, 1983