Zobrazeno 1 - 10
of 60
pro vyhledávání: '"C.Z. Serpan"'
Publikováno v:
Nuclear Engineering and Design. 171:1-14
Research at the Nuclear Regulatory Commission (Nrc) on the integrity and inspection of light water reactor (LWR) primary system materials and components, and on structural analysis, grew out of programs under way in the Atomic Energy Commission from
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9659ab50026b078e1b81b87497e6fde1
https://doi.org/10.1016/s0029-5493(96)01313-1
https://doi.org/10.1016/s0029-5493(96)01313-1
Publikováno v:
International Journal of Pressure Vessels and Piping. 54:99-105
Neutron transport calculations and the development of statistically based adjustment procedures have led to the demand for statistically based uncertainties for all input data. The three major sources of uncertainty in the calculational methodology w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f6282e68119e53e4b1d7a32fb8d5f9e
https://doi.org/10.1016/0308-0161(93)90129-h
https://doi.org/10.1016/0308-0161(93)90129-h
Autor:
C.Z. Serpan, K.R. Wichman
Publikováno v:
International Journal of Pressure Vessels and Piping. 54:267-277
As commercial nuclear power plants are being developed, the regulatory requirements in different countries for degradation of materials have typically been focused on the term of the operating plant license, be it 10 or 40 years, or simply from one o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0e0153a060d1e63d6bf8ee3a7adfe2d3
https://doi.org/10.1016/0308-0161(93)90137-i
https://doi.org/10.1016/0308-0161(93)90137-i
Autor:
C.Z. Serpan, Lendell E. Steele
Several such exposure criteria have been evaluated through use of the results of metallurgical tests of reference steel specimens after irradiation in light and heavy water moderated reactor environments as well as in graphite moderated reactor envir
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fadd971b3c5a0454bd8efb433b554be1
https://doi.org/10.1520/stp41339s
https://doi.org/10.1520/stp41339s
Autor:
L.E. Steele, C.Z. Serpan
Because of the self shielding and attenuation properties of the vessel material, a nuclear reactor pressure vessel will have a neutron flux and spectrum variation across its thickness. As a result of this variation, a pressure vessel should show vari
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a942a5b9a3fdaba5b4202d4d74a06370
https://doi.org/10.1520/stp43536s
https://doi.org/10.1520/stp43536s
Autor:
C.Z. Serpan, LE Steele
Publikováno v:
Analysis of Reactor Vessel Radiation Effects Surveillance Programs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2acde0d6a530450bc3adb4a012976f8f
https://doi.org/10.1520/stp28628s
https://doi.org/10.1520/stp28628s
Autor:
LE Steele, C.Z. Serpan
Publikováno v:
Analysis of Reactor Vessel Radiation Effects Surveillance Programs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::15c4f213a14f96f45111f6e9aaf61f9b
https://doi.org/10.1520/stp28625s
https://doi.org/10.1520/stp28625s
Autor:
C.Z. Serpan, LE Steele
Publikováno v:
Analysis of Reactor Vessel Radiation Effects Surveillance Programs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f70de8caa96a74919312f297c37c3d51
https://doi.org/10.1520/stp28626s
https://doi.org/10.1520/stp28626s
Autor:
LE Steele, C.Z. Serpan
Publikováno v:
Analysis of Reactor Vessel Radiation Effects Surveillance Programs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::58ab814cf64b9b547d2e0773bb220fa9
https://doi.org/10.1520/stp28629s
https://doi.org/10.1520/stp28629s