Results 21 to 30 of about 127,616,970 (139)

1000 Words

open access: yes, 2020
1000 Words is a leading online contemporary photography magazine. It commissions and publishes exhibition and photo book reviews, essays and interviews in response to the visual culture of our present moment.
Clark, Tim, 1000 Words
core   +6 more sources

A method for limitation of probability of accumulation of fuel elements claddings damage in WWER

open access: yesTrudy Odesskogo Politehničeskogo Universiteta, 2014
The aim is to reduce the probability of accumulation of fuel elements claddings damage by developing a method to control the properties of the fuel elements on stages of design and operation of WWER.
Сергій Миколайович Пелих   +2 more
doaj   +7 more sources

IMPROVING THE EFFICIENCY OF THE UNIT OF THE ZAPORIZHZHIA NPP WITH A WWER-1000 REACTOR

open access: yesProblems of Atomic Science and Technology, 2020
Improving the efficiency of the unit of the Zaporizhzhia NPP with a WWER-1000 reactor, by reducing the water temperature at the inlet to the condenser. The work describes the description of the NPP and the nuclear power reactor WWER-1000, by reducing the water temperature at the inlet to the condenser.
Cheilytko, A.A.   +2 more
openaire   +2 more sources

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]

open access: yesЯдерна 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

Comparative Study of Spectral Regulation Range of Excess Reactivity Control in Pressurized Water Reactors Using Zirconium Displacers for Uranium and Thorium Fuel Cycles

open access: yesГлобальная 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

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

open access: yesЯдерна фізика та енергетика, 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, the ...
Yu. Fylonych   +3 more
doaj   +1 more source

Reply to V. I. Borysenko's comment on the article: "Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000" [PDF]

open access: yesЯдерна 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

Decision support system for WWER-1000 reactivity management

open access: yesJournal of Physics: Conference Series, 2020
Abstract The article describes the developed software for automating operational calculations of reactivity changes of the water-water energetic reactor (WWER-1000). The main calculation dependencies, screen forms and test results on the Rostov nuclear power plant (Rostov NPP) are given. The calculation accuracy increase is shown.
M A Kolomiets   +2 more
openaire   +1 more source

On the Modelling of Thermal Aging through Neutron Irradiation and Annealing

open access: yesAdvances in Materials Science and Engineering, Volume 2018, Issue 1, 2018., 2018
A new method predicting long‐term thermal embrittlement of steel caused by P segregation is verified. The method is based on the results of impact strength or fracture toughness tests using specimens after relatively short‐term neutron irradiation followed by annealing.
Boris Margolin   +4 more
wiley   +1 more source

Gas‐Cooled Thorium Reactor with Fuel Block of the Unified Design

open access: yesAdvances in Materials Science and Engineering, Volume 2015, Issue 1, 2015., 2015
Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low‐power reactor systems correspond to the new technological platform.
Igor Shamanin   +4 more
wiley   +1 more source

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