Results 31 to 40 of about 674,656 (134)
Глобальная ядерная безопасность, 2022 The compensation for the excess reactivity in the pressurized water reactors WWER is realized with high neutron absorber materials. The traditional excess reactivity regulation methods lead to unfeasible neutron utilization and reduce the breeding ...
A. I. Elazaka +2 more
doaj +1 more source
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 +15 more
wiley +1 more source
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 +2 more
doaj
Reply to V. I. Borysenko's comment on the article: "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]
Ядерна фізика та енергетика, 2020 : Reply to V. I. Borysenko's 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" https://doi.org/10.15407 ...
V. I. Skalozubov +4 more
doaj +1 more source
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 +4 more
wiley +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 +4 more
wiley +1 more source
Mathematical Models for Investigation of WWER-1000/320 Transients
Nuclear and Radiation Safety, 2018 The paper presents mathematical models of the reactor WWER-1000/320, which are designed to investigate non-stationary operating modes of the reactor. The models in relative state variables include a point model of neutron kinetics with six groups of delayed neutrons and models of thermal processes, gradual heat generation, change in xenon concentration.
D. Lukinova, V. Severin, E. Nikulina
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The Use of Th in HTR: State of the Art and Implementation in Th/Pu Fuel Cycles
Science and Technology of Nuclear Installations, Volume 2009, Issue 1, 2009., 2009 Nowadays nuclear is the only greenhouse‐free source that can appreciably respond to the increasing worldwide energy demand. The use of Thorium in the nuclear energy production may offer some advantages to accomplish this task. Extensive R&D on the thorium fuel cycle has been conducted in many countries around the world.
Guido Mazzini +6 more
wiley +1 more source
Use of the Natural Circulation Flow Map for Natural Circulation Systems Evaluation
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 The aim of this paper is to collect and resume the work done to build and develop, at the University of Pisa, an engineering tool related to the natural circulation. After a brief description of the different loop flow regimes in single phase and two phase, the derivation of a suitable tool to judge the NC performance in a generic system is presented ...
M. Cherubini +4 more
wiley +1 more source
Brittle Fracture Probabilistic Assessment of WWER-1000 RPVs
Volume 3: Design and Analysis, 2014 This paper presents a methodology for brittle fracture probability assessment of WWER-1000 RPVs subjected to PTS. The main attention of the study is focused on the definition of the stochastic input data: fracture toughness, CTB, size and shape of the defects. Fracture toughness of RPV metal in the initial state is determined, separately
Igor Orynyak +4 more
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