Comparison of Маster curve with normative method of estimating WWER-1000 reactor pressure vessel metal fracture toughness

Autor: V. M. Revka, L. I. Chyrko

Publikováno v: Âderna Fìzika ta Energetika, Vol 25, Iss 1, Pp 58-65 (2024)

The paper considers the generalized temperature dependence of the stress intensity factor KJC in the WWER-1000 reactor pressure vessel metal, which was derived based on the surveillance test data for fracture toughness. The consistency of the shape o

Externí odkaz: https://doaj.org/article/ad60b45a377340299da35dab31778af8

НЕОПРЕДЕЛЕННОСТЬ В РАСЧЕТАХ ИЗ-ЗА «МГНОВЕННЫХ» АВАРИЙНЫХ СИТУАЦИЙ НА ВВЭР-1000

Autor: S. P. Nikonov, D. A. Amer

Publikováno v: Глобальная ядерная безопасность, Vol 0, Iss 1, Pp 62-72 (2022)

The paper shows the occurrence of pressure waves and their propagation in the equipment of the first circuit of the WWER-1000 reactor plant in emergency situations associated with an instantaneous stop of the Main circulation pump or a two-way flow w

Externí odkaz: https://doaj.org/article/df03659eaea548ecbdcf7309281af594

Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor

Autor: Yu. Fylonych, V. Zaporozhan, O. Balashevskyi, K. Merkotan

Publikováno v: Âderna Fìzika ta Energetika, Vol 22, Iss 1, Pp 48-55 (2021)

The developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, th

Externí odkaz: https://doaj.org/article/a9ffdab4bc184aefacea8682c20eca66

THE ASSESSMENT OF SAFETY SYSTEMS IN WWER-1000 NUCLEAR REACTOR USING IAEA SIMULATOR

Autor: Trần Đăng Khoa, Trịnh Thị Tú Anh

Publikováno v: Tạp chí Khoa học Đại học Đà Lạt, Vol 7, Iss 3, Pp 329-341 (2017)

In this study, the operation and response capability of safety system in nuclear reactor WWER-1000 was analyzed during the accidents that involved the failure of main circulation pump or feed water pumps. The nuclear reactor WWER-1000 simulator devel

Externí odkaz: https://doaj.org/article/ab8803a4ad0e43c7961c5530c0631d13

Сучасні підходи до розрахункового обґрунтування міцності критичних елементів обладнання реакторних установок АЕС з ВВЕР

Publikováno v: International Scientific and Technical conference "The Progressive Technics, Technology and Engineering Education"; No. XXIII (2023): PROGRESSIVE TECHNICS, TECHNOLOGY AND ENGINEERING EDUCATION
Матеріали науково-технічної конференції "Прогресивна техніка, технологія та інженерна освіта"; № XXIII (2023): ПРОГРЕСИВНА ТЕХНІКА, ТЕХНОЛОГІЯ ТА ІНЖЕНЕРНА ОСВІТА

This study presents the theoretical and applied results on the development and application of refined models and methods for solving actual problems of mechanics related to the substantiation of strength and forecasting the service life of elements o

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=scientific_p::465b2dab4c48111a7df3bcaf8299d18a
http://conf.mmi.kpi.ua/proc/article/view/280252