Results 21 to 30 of about 278 (148)

Estimation of local linear heat rate jump values in the variable loading mode [PDF]

Ядерна фізика та енергетика, 2011
A method of the WWER-1000 fuel element cladding durability analysis using the energy creep theory makes it possible to determinate the WWER-1000 reactor permissible operation time for the mode of varying loading. But the WWER-1000 axial segments and fuel
S. N. Pelykh, R. L. Gontar, T. V. Tsiselskaya   +2 more
doaj  

Analyses of the OSU‐MASLWR Experimental Test Facility

Science and Technology of Nuclear Installations, Volume 2012, Issue 1, 2012., 2012
Today, considering the sustainability of the nuclear technology in the energy mix policy of developing and developed countries, the international community starts the development of new advanced reactor designs. In this framework, Oregon State University (OSU) has constructed, a system level test facility to examine natural circulation phenomena of ...
F. Mascari, G. Vella, B. G. Woods, F. D′Auria, Alessandro Del Nevo   +4 more
wiley   +1 more source

Possibility of a life-time extension for wwer-1000 reactor pressure vessels beyond the design period

Trudy Odesskogo Politehničeskogo Universiteta, 2020
At present a life-time extension for WWER-1000 reactor pressure vessels is an actual issue in Ukraine. For a decision about the life-time extension it is needed to assess mechanical properties and the critical brittleness temperature TK for the RPV ...
Микола Геннадійович Голяк, Володимир Миколайович Ревка, Людмила Іванівна Чирко, Олександр Вікторович Тригубенко, Юрій Віталійович Чайковський   +4 more
doaj   +5 more sources

A New Fuel Design for Two Different HW Type Reactors

Science and Technology of Nuclear Installations, Volume 2011, Issue 1, 2011., 2011
A new fuel element (called CARA) designed for two different heavy water reactors (HWRs) is presented. CARA could match fuel requirements of both (one CANDU and one unique Siemens′s design) Argentine HW reactors. It keeps the heavier fuel mass density and hydraulic flow restriction in both reactors together with improving both thermomechanic and ...
Daniel O. Brasnarof, Armando C. Marino, Juan E. Bergallo, Luis E. Juanicó, Juan Pablo Ordóñez   +4 more
wiley   +1 more source

Starting Point, Keys and Milestones of a Computer Code for the Simulation of the Behaviour of a Nuclear Fuel Rod

Science and Technology of Nuclear Installations, Volume 2011, Issue 1, 2011., 2011
The BaCo code (“Barra Combustible”) was developed at the Atomic Energy National Commission of Argentina (CNEA) for the simulation of nuclear fuel rod behaviour under irradiation conditions. We present in this paper a brief description of the code and the strategy used for the development, improvement, enhancement, and validation of a BaCo during the ...
Armando C. Marino, Juan Pablo Ordóñez
wiley   +1 more source

Review of Available Data for Validation of Nuresim Two‐Phase CFD Software Applied to CHF Investigations

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
The NURESIM Project of the 6th European Framework Program initiated the development of a new‐generation common European Standard Software Platform for nuclear reactor simulation. The thermal‐hydraulic subproject aims at improving the understanding and the predictive capabilities of the simulation tools for key two‐phase flow thermal‐hydraulic processes
D. Bestion, H. Anglart, D. Caraghiaur, P. Péturaud, B. Smith, M. Andreani, B. Niceno, E. Krepper, D. Lucas, F. Moretti, M. C. Galassi, J. Macek, L. Vyskocil, B. Koncar, G. Hazi, Iztok Tiselj   +15 more
wiley   +1 more source

Comment on the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi. "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]

Ядерна фізика та енергетика, 2020
Comment to the article: V. I. Skalozubov, I. L. Kozlov, Yu. A. Komarov, O. A. Chulkin, O. I. Piontkovskyi. "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000", https://doi.org/10.15407/jnpae2019.02 ...
V. I. Borysenko
doaj   +1 more source

Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary side of the steam generator, for an integral pressurized water reactor is presented in this paper.
Junli Gou, Suizheng Qiu, Guanghui Su, Douna Jia, Xu Cheng   +4 more
wiley   +1 more source

ACOUSTIC MODELING AND PREVENTION OF VIBROACOUSTIC RESONANCES IN THE PRIMARY CIRCUIT OF NUCLEAR POWER PLANTS WITH WWER-1200 REACTORS

Надежность и качество сложных систем
Background. The commissioning of new nuclear power plants with WWER-1200 water-water energetic reactors, including the Akkuyu Nuclear Power Plant, requires a high level of operational safety and seismic resistance.
Konstantin N. Proskuryakov, Ragy M. N. H. Ismail, Marina S. Khvostova   +2 more
doaj   +1 more source

Role of Passive Safety Systems in Chinese Nuclear Power Development

Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009
Passive safety systems have been widely applied to advanced water‐cooled reactors, to enhance the safety of nuclear power plants. The ambitious program of the nuclear power development in China requires reactor concepts with high safety level. For the near‐term and medium‐term, the Chinese government decided for advanced pressurized water reactors with
X. Cheng, Y. H. Yang, Y. Ouyang, H. X. Miao, Dino A. Araneo   +4 more
wiley   +1 more source