nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A microstructural examination of irradiated reactor pressure vessel weld samples
|
Bischler, P.J.E |
|
2000 |
77 |
10 |
p. 629-640 12 p. |
artikel |
2 |
Application of the Master Curve in the ASME Code
|
Rosinski, S.T |
|
2000 |
77 |
10 |
p. 591-598 8 p. |
artikel |
3 |
Direct measurement of reactor pressure vessel steels fracture toughness: Master Curve concept and instrumented Charpy-V test
|
Serrano, M. |
|
2000 |
77 |
10 |
p. 605-612 8 p. |
artikel |
4 |
Editorial
|
Davies, Myrddin |
|
2000 |
77 |
10 |
p. iii-iv nvt p. |
artikel |
5 |
Examination of VVER-440 RPV steel re-irradiation behavior using materials from operating units
|
Shtrombakh, Ya.I |
|
2000 |
77 |
10 |
p. 585-590 6 p. |
artikel |
6 |
Irradiation surveillance data for an A508 forging and associated weld metal
|
Priest, R.H |
|
2000 |
77 |
10 |
p. 621-628 8 p. |
artikel |
7 |
JAPEIC's activity on aging issue related to neutron irradiation of RPV/RV materials
|
Kataoka, S |
|
2000 |
77 |
10 |
p. 569-574 6 p. |
artikel |
8 |
Master Curve characterization of the fracture toughness in unirradiated and irradiated RPV steels using full- and 1/3-size pre-cracked Charpy specimens
|
Lee, B.-S |
|
2000 |
77 |
10 |
p. 599-604 6 p. |
artikel |
9 |
Re-embrittlement behaviour of VVER-440 reactor pressure vessel weld material after annealing
|
Kohopää, J |
|
2000 |
77 |
10 |
p. 575-584 10 p. |
artikel |
10 |
Results and evaluations of irradiation surveillance programmes of lightwater reactors in Germany
|
Langer, R. |
|
2000 |
77 |
10 |
p. 613-620 8 p. |
artikel |