| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A determination of the benefits of annealing irradiated pressure vessel weldments
|
Lott, R.G.
|
|
1988
|
34 |
1-5 |
p. 155-170
16 p.
|
artikel
|
| 2 |
A new procedure for evaluating crack arrest in reactor vessels
|
Fabi, R.J.
|
|
1988
|
34 |
1-5 |
p. 227-236
10 p.
|
artikel
|
| 3 |
A simplified method for calculating the stress intensity factor at crack arrest
|
Fabi, R.J.
|
|
1988
|
34 |
1-5 |
p. 207-225
19 p.
|
artikel
|
| 4 |
Assurance of the integrity of the pressure circuits of the sizewell B nuclear power station
|
Currie, Tom
|
|
1988
|
34 |
1-5 |
p. 345-353
9 p.
|
artikel
|
| 5 |
Comments on the present practice of fatigue analysis of nuclear power plant components
|
Jansky, J.
|
|
1988
|
34 |
1-5 |
p. 143-154
12 p.
|
artikel
|
| 6 |
Crack initiation and crack growth during thermal shock tests in the reactor pressure vessel of the HDR under corrosive medium conditions
|
Neubrech, G.E.
|
|
1988
|
34 |
1-5 |
p. 187-205
19 p.
|
artikel
|
| 7 |
Demonstrating leak-before-break for CANDU heat transport piping
|
Kozluk, M.J.
|
|
1988
|
34 |
1-5 |
p. 255-263
9 p.
|
artikel
|
| 8 |
Discussions on session I
|
|
|
1988
|
34 |
1-5 |
p. 109-116
8 p.
|
artikel
|
| 9 |
Discussions on session II
|
|
|
1988
|
34 |
1-5 |
p. 293-305
13 p.
|
artikel
|
| 10 |
Discussions on session III
|
|
|
1988
|
34 |
1-5 |
p. 355-364
10 p.
|
artikel
|
| 11 |
Editorial Board
|
|
|
1988
|
34 |
1-5 |
p. IFC-
1 p.
|
artikel
|
| 12 |
Fracture behaviour of large scale pressure vessels in the hydrotest
|
Rintamaa, Rauno
|
|
1988
|
34 |
1-5 |
p. 265-291
27 p.
|
artikel
|
| 13 |
Implications of the surry piping failure for other nuclear and fossil units
|
Chexal, V.K.
|
|
1988
|
34 |
1-5 |
p. 331-343
13 p.
|
artikel
|
| 14 |
Impurity effects in BWR water chemistry
|
Fejes, Peter
|
|
1988
|
34 |
1-5 |
p. 47-57
11 p.
|
artikel
|
| 15 |
Index
|
|
|
1988
|
34 |
1-5 |
p. 365-369
5 p.
|
artikel
|
| 16 |
Leak-before-break: An integrated approach for high energy piping
|
Chexal, V.K.
|
|
1988
|
34 |
1-5 |
p. 237-254
18 p.
|
artikel
|
| 17 |
List of contributors
|
|
|
1988
|
34 |
1-5 |
p. xi-xvii
nvt p.
|
artikel
|
| 18 |
Mechanical methods of improving resistance to stress corrosion cracking in BWR piping systems
|
Abel, J.S.
|
|
1988
|
34 |
1-5 |
p. 17-29
13 p.
|
artikel
|
| 19 |
New options for improved steam generator U-bend integrity
|
Gutzwiller, J.E.
|
|
1988
|
34 |
1-5 |
p. 95-108
14 p.
|
artikel
|
| 20 |
On-line monitoring to assure structural integrity of nuclear reactor components
|
Kiss, E.
|
|
1988
|
34 |
1-5 |
p. 3-15
13 p.
|
artikel
|
| 21 |
Piping issues in nuclear systems in the USA
|
Taboada, A.
|
|
1988
|
34 |
1-5 |
p. 309-313
5 p.
|
artikel
|
| 22 |
Preface
|
Steele, L.E.
|
|
1988
|
34 |
1-5 |
p. v-vi
nvt p.
|
artikel
|
| 23 |
Recent experience in pressure vessel materials irradiation
|
Mager, T.R.
|
|
1988
|
34 |
1-5 |
p. 171-185
15 p.
|
artikel
|
| 24 |
Recent topics of flaw prevention
|
Furuya, S.
|
|
1988
|
34 |
1-5 |
p. 83-93
11 p.
|
artikel
|
| 25 |
Some reflections on attitudes and mind-sets concerning pressure vessel failure in nuclear reactors
|
Östberg, Gustaf
|
|
1988
|
34 |
1-5 |
p. 315-330
16 p.
|
artikel
|
| 26 |
Steam generator repair
|
Smith, K.
|
|
1988
|
34 |
1-5 |
p. 31-45
15 p.
|
artikel
|
| 27 |
Stress corrosion cracking of nuclear reactor pressure vessel and piping steels
|
Speidel, Markus O
|
|
1988
|
34 |
1-5 |
p. 119-142
24 p.
|
artikel
|
| 28 |
Weld overlay repairs from conception to long-term qualification
|
Riccardella, P.C.
|
|
1988
|
34 |
1-5 |
p. 59-82
24 p.
|
artikel
|
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