Összesen 2 találat.


001-es BibID:BIBFORM094050
Első szerző:Babics Péter Pál
Cím:Adaptation of BPVC Section XI Requirements : the operator's and the regulator's persepective / P., Babics, S., Ratkai, D., Szabo, Trampus, Péter
ISBN:9780791843703 9780791838549
Tárgyszavak:Műszaki tudományok Gépészeti tudományok könyvfejezet
Megjelenés:Proceedings of the ASME Pressure Vessels and Piping Conference / edited by ASME Pressure. - p. 521-529. -
További szerzők:Rátkai Sándor (mérnök) Szabo D. (mérnök) Trampus Péter (1947-) (gépészmérnök)
Internet cím:Intézményi repozitóriumban (DEA) tárolt változat


001-es BibID:BIBFORM009350
Első szerző:Trampus Péter (gépészmérnök)
Cím:Comprehensive adaptation of the ASME Code at Paks NPP, Hungary / Peter Trampus, Peter Pal Babics
Megjegyzések:Chapter 65, co-authored by Peter Trampus and Peter Pal Babics, provides an overview on the recent activity in Hungary concerning comprehensive adaptation of the ASME Code. The owner of Paks NPP, Hungary's sole nuclear generating facility, is aiming at adjusting the ISI and IST program to meet ASME Code requirements. The objective is to achieve an internationally acceptable level in structural and functional integrity assessment of long-lived and passive as well as of active components, and to create the basis for a proper ageing management program in the operations period beyond the design life of the units. Apart from this, it will allow to extend the current four-year inspection interval for Class 1 components up to an eight-year one, which will contribute to a more cost-efficient operation and maintenance. The Hungarian nuclear regulatory regime gives an opportunity for this because the nuclear safety rules do not determine explicitly the applicable codes neither for the design nor for the ISI / IST. The Chapter briefly describes the background of the Paks life extension project and its regulatory aspects. The basic regulatory principles related to ASME adaptation are summarized. They focus on aspects of maintaining the current licensing basis as well as on the necessity to demonstrate the compliance with Section III requirements. The substantial part of the work is the design review of Class 1 and 2 components and, if needed, a re-design of selected components to comply with the Section III requirements. As an example for the ongoing design review process, the comparison of Fatigue Strength Reduction Factors for welds in pressure vessels and piping is presented.
Tárgyszavak:Műszaki tudományok Gépészeti tudományok könyvfejezet
nuclear power plant
life extension
in-service inspection
Megjelenés:Companion guide to the ASME boiler & pressure vessel code / editor, K. R. Rao. - p. 579-599. -
További szerzők:Babics Péter Pál
Internet cím:elektronikus változat
Rekordok letöltése1