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                             86 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A leak-before-break strategy for CANDU primary piping systems Aggarwal, M.L.
1986
120-121 1-4 p. 239-256
18 p.
artikel
2 A method for LEFM analysis of RPV during SBLOCA Iskander, S.K.
1986
120-121 1-4 p. 279-298
20 p.
artikel
3 Analyses and repair of defects found in the primary collector weld seams of the steam generators at loviisa nuclear power station Ahlstrand, R.
1986
120-121 1-4 p. 3-15
13 p.
artikel
4 Applicability of pipelocks as a remedy for intergranular stress corrosion cracking in BWRs Abel, J.S.
1986
120-121 1-4 p. 25-46
22 p.
artikel
5 Application of an ultrasonic data recording and processing system to reactor pressure vessel examination Buxbaum, S.R.
1988
120-121 1-4 p. 307-320
14 p.
artikel
6 Appraisal of elastic follow-up for a generic mechanical structure through two simplified methods Gamboni, S.
1989
120-121 1-4 p. 221-241
21 p.
artikel
7 Assessment of the influence of flaws on structural degradation and alternatives for repair and replacement Stahlkopf, K.E.
1986
120-121 1-4 p. 453-473
21 p.
artikel
8 Assessment of the integrity of structures containing defects Milne, I
1988
120-121 1-4 p. 3-104
102 p.
artikel
9 Background to and validation of CEGB report R/H/R6—Revision 3 Milne, I
1988
120-121 1-4 p. 105-196
92 p.
artikel
10 Class 2 piping rules in elevated temperature applications compared with class 1 prescriptions for LMFBRs Capello, R.
1989
120-121 1-4 p. 263-278
16 p.
artikel
11 Code aspects of life extension Raju, P.P.
1989
120-121 1-4 p. 189-199
11 p.
artikel
12 Code rules for fatigue analysis of crack-like discontinuities and small cracks Roche, Roland L.
1989
120-121 1-4 p. 201-218
18 p.
artikel
13 Comparative evaluation of preventive measures against primary side stress corrosion cracking of mill annealed inconel 600 steam generator tubes Frédérick, G.
1986
120-121 1-4 p. 47-67
21 p.
artikel
14 Considerations on the manner of accounting for fast fracture risk in the design of PWR vessels Pellissier-Tanon, A.
1986
120-121 1-4 p. 217-229
13 p.
artikel
15 Critical examination of valve design according to sub-section B 3500 of the french design and construction rules for mechanical components of PWR nuclear Islands (RCCM January 1985 edition) Huet, J.
1989
120-121 1-4 p. 279-299
21 p.
artikel
16 Current and planned activities at the PVRC in support of elevated temperature design technology Pai, David H.
1989
120-121 1-4 p. 67-79
13 p.
artikel
17 Defect detection and signal processing for cast stainless steel Shankar, R.
1988
120-121 1-4 p. 57-72
16 p.
artikel
18 Derivation of design curves for the elevated temperature fatigue endurance of type 316 stainless steel Wood, D.S.
1989
120-121 1-4 p. 171-188
18 p.
artikel
19 Description of the PISC III round robin test on cast stainless steel (CCSSRRT) and evaluation of results Doctor, S.
1988
120-121 1-4 p. 3-15
13 p.
artikel
20 Development of design procedures for fast reactors in the United Kingdom Rose, R.T.
1989
120-121 1-4 p. 99-112
14 p.
artikel
21 Development of procedures for the assessment of defects at elevated temperature Ainsworth, R.A.
1989
120-121 1-4 p. 141-153
13 p.
artikel
22 Discussion on session III—Advanced UT systems and their application Nichols, R.W.
1988
120-121 1-4 p. 331-333
3 p.
artikel
23 Discussion on session II—The PISC II parametric studies programme Crutzen, S.
1988
120-121 1-4 p. 247-258
12 p.
artikel
24 Discussion on session I—NDE of austenitic and dissimilar-metal welds Dau, G.
1988
120-121 1-4 p. 73-76
4 p.
artikel
25 Discussion on session IV—Future work in PISC III Nichols, R.W.
1988
120-121 1-4 p. 337-343
7 p.
artikel
26 Discussions on session I Stahlkopf, K.E.
1986
120-121 1-4 p. 139-151
13 p.
artikel
27 Discussions on session II Steele, L.E.
1986
120-121 1-4 p. 299-309
11 p.
artikel
28 Discussions on session III Steele, L.E.
1986
120-121 1-4 p. 447-450
4 p.
artikel
29 Editorial Nichols, R.W.
1988
120-121 1-4 p. 1-
1 p.
artikel
30 Editorial Board 1989
120-121 1-4 p. IFC-
1 p.
artikel
31 Editorial Board 1986
120-121 1-4 p. IFC-
1 p.
artikel
32 Editorial Board 1988
120-121 1-4 p. IFC-
1 p.
artikel
33 Editorial Board 1988
120-121 1-4 p. IFC-
1 p.
artikel
34 EMAT and multifrequency eddy current testing on test block no. 81-1192-EMT Hübschen, G.
1988
120-121 1-4 p. 189-199
11 p.
artikel
35 European R & D co-ordinate programme on structural integrity of fast breeder reactors Hoffmann, A.
1989
120-121 1-4 p. 127-140
14 p.
artikel
36 Experience in the replacement of safety related piping in German boiling water reactors Kussmaul, K.
1986
120-121 1-4 p. 111-138
28 p.
artikel
37 Feature enhanced ultrasonic imaging—Application of signal processing and analysis Shankar, R.
1988
120-121 1-4 p. 261-276
16 p.
artikel
38 Flaw analysis in steam generator tubes Hutin, J.-P.
1986
120-121 1-4 p. 267-278
12 p.
artikel
39 German codes and standards for nuclear power plant components, recent KTA activities for advanced reactor types Bieniussa, K.
1989
120-121 1-4 p. 113-126
14 p.
artikel
40 Hydrogen water chemistry operating experience Cowan, R.L.
1986
120-121 1-4 p. 313-331
19 p.
artikel
41 IHSI application to the welded joint with small cracks Okamoto, A.
1986
120-121 1-4 p. 393-412
20 p.
artikel
42 Improvement of structural integrity of LWR components Ando, Y.
1986
120-121 1-4 p. 413-445
33 p.
artikel
43 Index 1986
120-121 1-4 p. 475-481
7 p.
artikel
44 Index 1988
120-121 1-4 p. 345-349
5 p.
artikel
45 Index 1989
120-121 1-4 p. 301-305
5 p.
artikel
46 Influence of repair welding on cyclic thermal shock behaviour of a RPV nozzle corner Kussmaul, K.
1986
120-121 1-4 p. 89-109
21 p.
artikel
47 Integrated appraisal of the results relative to the effect of defect characteristics Crutzen, S.
1988
120-121 1-4 p. 171-
1 p.
artikel
48 Interim structural design criteria for fusion reactor components Zolti, E.
1989
120-121 1-4 p. 53-66
14 p.
artikel
49 List of contributors 1989
120-121 1-4 p. xi-xiv
nvt p.
artikel
50 List of contributors 1986
120-121 1-4 p. xiii-xviii
nvt p.
artikel
51 List of contributors 1988
120-121 1-4 p. xiii-xvi
nvt p.
artikel
52 Methodology for repair/replacement decisions for flawed components Iida, K.
1986
120-121 1-4 p. 155-183
29 p.
artikel
53 Methods for preventing steam generator failure or degradation Green, S.J.
1986
120-121 1-4 p. 359-391
33 p.
artikel
54 Monticello recirculation piping replacement problems, contingencies, and evolving work scope Neils, G.H.
1986
120-121 1-4 p. 69-74
6 p.
artikel
55 On the trustworthiness of safety assessments for nuclear pressure vessels Östberg, G.
1986
120-121 1-4 p. 257-266
10 p.
artikel
56 Parametric studies on the effect of defect characteristics on their detection and sizing by ultrasound Certo, M.
1988
120-121 1-4 p. 89-118
30 p.
artikel
57 Parametric study on the effect of UT equipment characteristics (EEC) on detection, location and sizing Lakestani, F.
1988
120-121 1-4 p. 201-205
5 p.
artikel
58 PISC-III action on dissimilar-metal welds Borloo, E.E.
1988
120-121 1-4 p. 29-35
7 p.
artikel
59 PISC III phase 2 programme on stainless steel samples Muscara, J.
1988
120-121 1-4 p. 17-28
12 p.
artikel
60 PISC II parametric studies Borloo, E.E.
1988
120-121 1-4 p. 207-212
6 p.
artikel
61 PISC II parametric study on flaw characterisation using the tandem and TOFD techniques Murgatroyd, R.A.
1988
120-121 1-4 p. 137-169
33 p.
artikel
62 PISC II parametric study on the effect of the cladding Beurdeley, Y.
1988
120-121 1-4 p. 213-245
33 p.
artikel
63 PISC parametric study on the effect of defect characteristics on immersion focusing probe testing results Dombret, Ph.
1988
120-121 1-4 p. 119-135
17 p.
artikel
64 Practical procedure for stress classification Roche, Roland L.
1989
120-121 1-4 p. 27-44
18 p.
artikel
65 Preface Nichols, R.W.
1988
120-121 1-4 p. v-vii
nvt p.
artikel
66 Preface 1989
120-121 1-4 p. v-vi
nvt p.
artikel
67 Preface Steele, L.E.
1986
120-121 1-4 p. v-vii
nvt p.
artikel
68 Prevention of bolting degradation or failure in pressure boundary and support applications Merrick, E.A.
1986
120-121 1-4 p. 333-357
25 p.
artikel
69 Principles of the German approach to the analysis of flawed structures Kussmaul, K.
1986
120-121 1-4 p. 185-215
31 p.
artikel
70 Reasons for crack closure and possibilities for detection and sizing by NDE Deuster, G.
1988
120-121 1-4 p. 173-188
16 p.
artikel
71 Recent experimental research into buckling design methods for FBR components Yuhara, Tetsuo
1989
120-121 1-4 p. 243-261
19 p.
artikel
72 Recent Italian research and development of the high temperature design method Corsi, F.
1989
120-121 1-4 p. 93-98
6 p.
artikel
73 Review of limit loads of structures containing defects Miller, A.G.
1988
120-121 1-4 p. 197-327
131 p.
artikel
74 Ringhals No. 2—Steam generator repair/replacement options Hunyadi, L.
1986
120-121 1-4 p. 75-87
13 p.
artikel
75 Simplified elastoplastic fatigue analysis Autrusson, B.
1989
120-121 1-4 p. 157-169
13 p.
artikel
76 SIRACUS, an expert system to help inspectors in characterizing detected defects Bieth, M.
1988
120-121 1-4 p. 321-329
9 p.
artikel
77 Some notes on the structural design code for FBR components Wada, Hiroshi
1989
120-121 1-4 p. 83-92
10 p.
artikel
78 Some problems in analytical design Fangyu, Gu
1989
120-121 1-4 p. 45-52
8 p.
artikel
79 Survey and comparison of automated UT systems Neeley, V.I.
1988
120-121 1-4 p. 277-291
15 p.
artikel
80 Tennessee valley authority experience with field application of advanced UT system Sasahara, T.
1988
120-121 1-4 p. 293-306
14 p.
artikel
81 The purpose of the PISC II parametric studies programme Birac, C.
1988
120-121 1-4 p. 79-87
9 p.
artikel
82 The regulator's role in code development Currie, T.
1989
120-121 1-4 p. 17-26
10 p.
artikel
83 Ultrasonic examination of dissimilar-metal welds in BWR and PWR plants Ammirato, F.
1988
120-121 1-4 p. 37-56
20 p.
artikel
84 United states criteria for repair and replacement of BWR piping and steam generator tubing Vollmer, R.H.
1986
120-121 1-4 p. 231-238
8 p.
artikel
85 Weld overlay of BWR flawed piping Edwards, N.W.
1986
120-121 1-4 p. 17-24
8 p.
artikel
86 What's new in design requirements in the 1986 edition and 1986 addenda of section III, Div. 1, of the ASME boiler and pressure vessel code Farr, James R.
1989
120-121 1-4 p. 3-15
13 p.
artikel
                             86 gevonden resultaten
 
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