Zobrazeno 1 - 10
of 63
pro vyhledávání: '"J.G. Blauel"'
Publikováno v:
Nuclear Engineering and Design. 190:149-158
If cracks are postulated in the ferritic base material beneath the austenitic cladding, their initiation and propagation under hypothetical loading cases is influenced by the load carrying capacity of the cladding. The toughness of the KKS-RPV claddi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a6a36d964f12877896403cc82a96cb2f
https://doi.org/10.1016/s0029-5493(98)00320-3
https://doi.org/10.1016/s0029-5493(98)00320-3
Publikováno v:
Nuclear Engineering and Design. 174:237-246
During emergency core cooling situations, the criticality of hypothetical cracks located in the ferritic base material beneath the austenitic cladding is strongly influenced by the integrity of the cladding: if the cladding is intact, the crack tip l
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::13f63f3abac7f5f106f849aa8face7eb
https://doi.org/10.1016/s0029-5493(97)00135-0
https://doi.org/10.1016/s0029-5493(97)00135-0
Effect of cladding on the initiation behaviour of finite length cracks in an RPV under thermal shock
Publikováno v:
Nuclear Engineering and Design. 171:179-188
An analytical method has been developed and verified by three-dimensional elastic-plastic finite element analyses to evaluate stress intensity factors for finite length through clad and subclad cracks in reactor pressure vessels (RPV) under loss of c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::58f32e5799959e301dc68820f8a01b51
https://doi.org/10.1016/s0029-5493(96)01325-8
https://doi.org/10.1016/s0029-5493(96)01325-8
Publikováno v:
Nuclear Engineering and Design. 144:45-52
Two specific problems within the safety case of Stade RPV have been analysed: brittle fracture initiation and arrest under strip type emergency core cooling conditions and safety margins against ductile failure from deep cracks as postulated by ASME-
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::04e83b185046d5fd1c70836f53d21f46
https://doi.org/10.1016/0029-5493(93)90007-v
https://doi.org/10.1016/0029-5493(93)90007-v
Publikováno v:
Scripta Metallurgica et Materialia. 26:1411-1416
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1dce40860b0e31dc8a930b350a60d456
https://doi.org/10.1016/0956-716x(92)90658-2
https://doi.org/10.1016/0956-716x(92)90658-2
The effect of warm prestressing has been investigated representative for the core weld metal of the RPV Stade. Model experiments on CT specimens show a significant rise of effective fracture toughness Keff after warm prestressing and the conservative
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60d5d52bd001d134caf5e50068682f68
https://publica.fraunhofer.de/handle/publica/197933
https://publica.fraunhofer.de/handle/publica/197933
To investigate the effect of the cladding on the behaviour of postulated near surface cracks in the wall of a nuclear pressure vessel under thermal shock transients, two model experiments on cladded plates with artificially introduced cracks were per
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::710b4b500564b0843221ebf672df1fac
https://publica.fraunhofer.de/handle/publica/195498
https://publica.fraunhofer.de/handle/publica/195498
Extending the safety analysis of a nuclear reactor pressure vessel beyond the requirements of the regulations which were first laid down in the ASME-Code, the behavior of two crack sizes ( 1 4 - t axial, 3 4 - t circumferential, a 2 c = 1 6 ) in the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::dcde376dcb01f936341496d7bda048f2
https://publica.fraunhofer.de/handle/publica/178176
https://publica.fraunhofer.de/handle/publica/178176
Publikováno v:
Nuclear Engineering and Design. 94:233-239
The effect of warm prestressing (WPS) has been investigated for the specific material and loading conditions of the central circumferential weld of the reactor pressure vessel of KKS under emergency core cooling. Warm prestressing results in a signif
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a9b332590672d82f8ee1fca24f2a7e2e
https://doi.org/10.1016/0029-5493(86)90005-1
https://doi.org/10.1016/0029-5493(86)90005-1