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                             28 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of flow distribution in a PWR fuel rod bundle model containing a blockage - Part 1. A 61% coplanar blockage Ang, M.L.
1988
108 3 p. 275-294
20 p.
artikel
2 Analysis of flow distribution in a PWR fuel rod bundle model containing a blockage - Part 2. A non-coplanar blockage Ang, M.L.
1988
108 3 p. 295-314
20 p.
artikel
3 Announcements 1988
108 3 p. 529-531
3 p.
artikel
4 Author index to volume 108 1988
108 3 p. 533-535
3 p.
artikel
5 A weir model to relate the liquid flow rate with the water level in an inverted u-bend Lin, W.K.
1988
108 3 p. 395-401
7 p.
artikel
6 Crack resistance properties of through-cracks in austenitic straight pipes (DN 700) under bending Grüter, L.
1988
108 3 p. 447-455
9 p.
artikel
7 Design aspects and pertaining development work for the KWU 200 MWth nuclear heating reactor Bittermann, Dietmar
1988
108 3 p. 403-417
15 p.
artikel
8 Dynamic analysis and response spectra for the main process building of a reprocessing plant Hilpert, H.-J.
1988
108 3 p. 437-445
9 p.
artikel
9 Effect of boiling on particle drag Cho, D.H.
1988
108 3 p. 523-524
2 p.
artikel
10 Energy transfer mechanisms in LMR rod bundles under mixed convection conditions Ro, Tae Sun
1988
108 3 p. 343-357
15 p.
artikel
11 Experiments on the load following behaviour of PWR fuel rods Fischer, G.
1988
108 3 p. 429-432
4 p.
artikel
12 Failure behaviour of steels with different levels of strength and toughness Hubo, R.
1988
108 3 p. 457-466
10 p.
artikel
13 Fatigue and creep crack growth in methane reformer tubes at temperatures above 700°C Rödig, M
1988
108 3 p. 467-476
10 p.
artikel
14 Filtered bessel functions in computerized tomography Rathore, R.K.S.
1988
108 3 p. 375-383
9 p.
artikel
15 Iodine removal by condensation from containment atmosphere in post external event conditions Ketter, A.
1988
108 3 p. 385-393
9 p.
artikel
16 J-integral estimation analysis for circumferential throughwall cracked pipes Zahoor, Akram
1988
108 3 p. 515-522
8 p.
artikel
17 Load-displacement relation of reactor buildings subjected to earthquake forces Inada, Yasuo
1988
108 3 p. 497-514
18 p.
artikel
18 Measurement of a large BWR's spatial stability Thie, J.A.
1988
108 3 p. 525-527
3 p.
artikel
19 On the two-region rewetting model with a step change in the heat transfer coefficient Olek, Shmuel
1988
108 3 p. 315-322
8 p.
artikel
20 Predicted and measured response of the EBR-II plant to large steam pressure changes Feldman, E.E.
1988
108 3 p. 331-341
11 p.
artikel
21 Solutions of the neutronic design problems of small heating reactor cores based on the BWR principle Foskolos, K.
1988
108 3 p. 419-427
9 p.
artikel
22 Standardization of piping supports in nuclear power plants using pretested components Lauer, J.
1988
108 3 p. 477-483
7 p.
artikel
23 State of the art in the manufacture of heavy forgings for reactor components in the Federal Republic of Germany Erve, M.
1988
108 3 p. 485-495
11 p.
artikel
24 Stochastic analysis of mechanical vibrations in reactors Taleyarkhan, R.P.
1988
108 3 p. 369-373
5 p.
artikel
25 Subject index to volume 108 1988
108 3 p. 537-539
3 p.
artikel
26 The BWR hybrid 4 control rod Gross, H.
1988
108 3 p. 433-436
4 p.
artikel
27 The effect of precursory cooling on rewetting of a slab Olek, Shmuel
1988
108 3 p. 323-330
8 p.
artikel
28 Thermal and hydraulic tests in hendel T2 supporting the development of the core bottom structure of the High Temperature Engineering Test Reactor (HTTR) Kunitomi, K
1988
108 3 p. 359-368
10 p.
artikel
                             28 gevonden resultaten
 
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