| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Application of the advanced instrumented impact testing facility for the irradiation damage assessment
|
Rintamaa, Rauno
|
|
1993
|
55 |
1 |
p. 89-106
18 p.
|
artikel
|
| 2 |
Comparison of Charpy-V and J-Integral transition temperature shifts in CrMoV pressure vessel steels
|
Valo, M.
|
|
1993
|
55 |
1 |
p. 81-88
8 p.
|
artikel
|
| 3 |
Editorial Board
|
|
|
1993
|
55 |
1 |
p. IFC-
1 p.
|
artikel
|
| 4 |
Effect of cladding residual stresses on J-integrals in a pressure vessel
|
Rajamäki, P.
|
|
1993
|
55 |
1 |
p. 125-139
15 p.
|
artikel
|
| 5 |
Guest editorial
|
Törrönen, Kari
|
|
1993
|
55 |
1 |
p. 1-2
2 p.
|
artikel
|
| 6 |
Irradiation damage effects on the fracture toughness transition curve shape for reactor pressure vessel steels
|
Wallin, K.
|
|
1993
|
55 |
1 |
p. 61-79
19 p.
|
artikel
|
| 7 |
Nordic numerical round robin for a side-grooved CT-specimen
|
Talja, Heli
|
|
1993
|
55 |
1 |
p. 107-123
17 p.
|
artikel
|
| 8 |
On-line monitoring for further corrosion reduction and better understanding of the activity build-up in LWR primary coolant systems
|
Mäkelä, K.
|
|
1993
|
55 |
1 |
p. 163-177
15 p.
|
artikel
|
| 9 |
Overview of the nuclear power plant structural integrity research in Finland
|
Törrönen, K.
|
|
1993
|
55 |
1 |
p. 3-59
57 p.
|
artikel
|
| 10 |
Post conference seminar No. 2 assuring structural integrity of steel reactor pressure boundary components
|
|
|
1993
|
55 |
1 |
p. 179-180
2 p.
|
artikel
|
| 11 |
The correlation of IGSCC propagation with the power plant transient history
|
Aaltonen, P.
|
|
1993
|
55 |
1 |
p. 149-162
14 p.
|
artikel
|
| 12 |
12th International conference on structural mechanics in reactor technology
|
|
|
1993
|
55 |
1 |
p. 179-
1 p.
|
artikel
|
| 13 |
Ultrasonic sizing of defects in the austenitic cladding of reactor pressure vessels
|
Kauppinen, P.
|
|
1993
|
55 |
1 |
p. 141-147
7 p.
|
artikel
|
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