| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accurate fracture mechanics analysis methods for subsurface or surface defects, including their interaction with the cladding
|
Pellissier-Tanon, A.
|
|
1993
|
54 |
1-2 |
p. 231-257
27 p.
|
artikel
|
| 2 |
An aging management approach for pressurized water reactor pressure vessels
|
Shah, V.N.
|
|
1993
|
54 |
1-2 |
p. 317-340
24 p.
|
artikel
|
| 3 |
Approach and methodology for condition assessment of thermal reactor pressure vessels
|
English, C.A.
|
|
1993
|
54 |
1-2 |
p. 49-87
39 p.
|
artikel
|
| 4 |
A PWR pressure vessel safety assessment
|
Noël, Robert L.
|
|
1993
|
54 |
1-2 |
p. 293-316
24 p.
|
artikel
|
| 5 |
A regulatory view of irradiation embrittlement
|
Boydon, F.M.D.
|
|
1993
|
54 |
1-2 |
p. 279-292
14 p.
|
artikel
|
| 6 |
Charpy specimen reconstitution as a means of providing data for plex licencing purposes
|
Vandermeulen, W.
|
|
1993
|
54 |
1-2 |
p. 89-98
10 p.
|
artikel
|
| 7 |
Editorial Board
|
|
|
1993
|
54 |
1-2 |
p. IFC-
1 p.
|
artikel
|
| 8 |
Flux reduction and other mitigation measures for RPVs
|
Ahlstrand, Ralf
|
|
1993
|
54 |
1-2 |
p. 259-266
8 p.
|
artikel
|
| 9 |
Inspection performance with a view to pressure vessel life management
|
Crutzen, S.
|
|
1993
|
54 |
1-2 |
p. 107-136
30 p.
|
artikel
|
| 10 |
Introductory remarks
|
Forstén, Jarl
|
|
1993
|
54 |
1-2 |
p. 3-8
6 p.
|
artikel
|
| 11 |
Low temperature embrittlement of LWR RPV support structures
|
McElroy, R.J.
|
|
1993
|
54 |
1-2 |
p. 171-211
41 p.
|
artikel
|
| 12 |
NEA/CSNI workshop on the safety assessment of reactor pressure vessels
|
Törrönen, Kari
|
|
1993
|
54 |
1-2 |
p. 1-
1 p.
|
artikel
|
| 13 |
Neutron fluence determination and uncertainty analysis
|
Kam, F.B.K.
|
|
1993
|
54 |
1-2 |
p. 99-105
7 p.
|
artikel
|
| 14 |
Phenomena of material degradation with time relevant to reactor pressure vessels
|
Hänninen, H
|
|
1993
|
54 |
1-2 |
p. 9-30
22 p.
|
artikel
|
| 15 |
Pressure vessel steel surveillance program: Developments, experience feed-back and perspectives
|
Barthelet, B.
|
|
1993
|
54 |
1-2 |
p. 157-170
14 p.
|
artikel
|
| 16 |
Reactor pressure vessel functionality issues and the development of a low temperature overpressurization transient limit for precluding crack initiation
|
Hijeck, Paul J.
|
|
1993
|
54 |
1-2 |
p. 213-230
18 p.
|
artikel
|
| 17 |
Reliability assessment by aid of probabilistic fracture mechanics
|
Nilsson, Fred
|
|
1993
|
54 |
1-2 |
p. 341-352
12 p.
|
artikel
|
| 18 |
Review of thermal ageing data and its application to operating reactor pressure vessels
|
Vatter, I.A.
|
|
1993
|
54 |
1-2 |
p. 31-48
18 p.
|
artikel
|
| 19 |
Review of the state of the art in the assessment for material degradation with time
|
Kussmaul, K.
|
|
1993
|
54 |
1-2 |
p. 137-156
20 p.
|
artikel
|
| 20 |
Summary and conclusions of the workshop on the safety assessment of reactor pressure vessels
|
Törrönen, K.
|
|
1993
|
54 |
1-2 |
p. 353-361
9 p.
|
artikel
|
| 21 |
The philosophy and technical bases of current regulatory requirements regarding material degradation with time
|
Serpan Jr., Charles Z.
|
|
1993
|
54 |
1-2 |
p. 267-277
11 p.
|
artikel
|
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