Zobrazeno 1 - 10
of 35
pro vyhledávání: '"M. Erve"'
Autor:
M. Erve
Publikováno v:
Nuclear Engineering and Design. 193:337-347
The life-limiting mechanisms for components and systems are physical aging and wear. Both of them are related to changes of microstructure in the bulk material or at the phase boundaries medium/material and material/material. They are triggered durin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::907a3357a706bb9385f0a54572782991
https://doi.org/10.1016/s0029-5493(99)00189-2
https://doi.org/10.1016/s0029-5493(99)00189-2
Publikováno v:
Nuclear Engineering and Design. 191:285-292
The safety of the RPV of the Bulgarian NPP Kozloduy Unit 1 was analysed within EC-financed contracts according to a pressurized-thermal-shock- (PTS-) procedure applied in Germany (Erve, M., Hertlein, R., 1991. Post SMiRT Seminar No 11, August 1991),
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7cf0fe2c8d406f71837a2342c86d7119
https://doi.org/10.1016/s0029-5493(99)00117-x
https://doi.org/10.1016/s0029-5493(99)00117-x
Publikováno v:
Nuclear Engineering and Design. 190:41-56
As visual examinations carried out in autumn 1994 detected cracks in a German BWR plant due to intergranular stress corrosion cracking (IGSCC) in several core shroud components manufactured from 1.4550 steel, precautionary examinations and assessment
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b0db503d217828bbef3b600bc43d53ec
https://doi.org/10.1016/s0029-5493(98)00309-4
https://doi.org/10.1016/s0029-5493(98)00309-4
Publikováno v:
Nuclear Engineering and Design. 171:125-136
After intergranular stress corrosion cracking had been found in piping, made from stabilized austenitic stainless steel, carrying reactor water in German BWRs, remedial measures have been taken with regard to the refurbishing concepts, material consi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0a74422855d06a70237bbabf1cc755dd
https://doi.org/10.1016/s0029-5493(96)01311-8
https://doi.org/10.1016/s0029-5493(96)01311-8
Publikováno v:
Nuclear Engineering and Design. 171:113-123
Cracks have been found in the welds of piping systems made from stabilized austenitic stainless steels in German boiling water reactors (BWR). In the course of the intensive failure analysis metallographic examinations, microstructural investigations
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::124a52dca7d1c329d04ac4876c679a87
https://doi.org/10.1016/s0029-5493(96)01320-9
https://doi.org/10.1016/s0029-5493(96)01320-9
Publikováno v:
Nuclear Engineering and Design. 151:373-386
The safety analysis of reactor pressure vessels has to take into account all parameters, including design, material, fabrication, inspection, loading and service conditions. This safety analysis for pressurized thermal shock consists of the following
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bbb1c978291a3000af144821f040bb78
https://doi.org/10.1016/0029-5493(94)90182-1
https://doi.org/10.1016/0029-5493(94)90182-1
Autor:
E. Tenckhoff, M. Erve
Publikováno v:
Nuclear Engineering and Design. 144:139-148
The safety standard which is attained at the time of initial startup by a nuclear power plant built in accordance with state-of-the-art design and engineering principles must be assured throughout the plant's entire lifetime. Based on operating exper
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::536cc840b055731700fb8caac56d4b1c
https://doi.org/10.1016/0029-5493(93)90015-2
https://doi.org/10.1016/0029-5493(93)90015-2
Publikováno v:
Kerntechnik. 57:353-359
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b9fd8ca725c4f5053124aaf8024b1f4c
https://doi.org/10.1515/kern-1992-570607
https://doi.org/10.1515/kern-1992-570607
Autor:
G. Bartholomé, M. Erve
Publikováno v:
Nuclear Engineering and Design. 128:103-114
The adequate margin of safety reached in the as-built condition for a nuclear power plant shall be maintained throughout the whole life of the plant. To attain this, a systematic lifetime evaluation of safety related items should be performed in due
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::47c18dd7fc9e8c58af5b11de34a539f6
https://doi.org/10.1016/0029-5493(91)90254-f
https://doi.org/10.1016/0029-5493(91)90254-f
Autor:
M. Erve
Publikováno v:
Kerntechnik. 55:329-334
This paper describes essential materials as used within the framework of the material concept for light water reactors built by Siemens and comments on their mechanical properties and operational behavior
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::147a1e36dc4bae005cc09ae8e27ec89e
https://doi.org/10.1515/kern-1990-550605
https://doi.org/10.1515/kern-1990-550605