Results 61 to 70 of about 705,564 (243)

Возможность использования альтернативных выгорающих поглотителей в реакторе ВВЭР-1000 [PDF]

, 2016
Объектом исследования является водо-водяной реактор ВВЭР-1000 с топливом в виде диоксида урана. Цель работы ― исследование возможности повышения глубины выгорания ядерного топлива в реакторе ВВЭР-1000.
Сливин, Алексей Асхарович
core  

Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz, Senem Şentürk Lüle, Han Zhang   +2 more
wiley   +1 more source

Data‐Driven and Precursor‐Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark

Science and Technology of Nuclear Installations, Volume 2019, Issue 1, 2019., 2019
A new data‐driven sampling‐based framework was developed for uncertainty quantification (UQ) of the homogenized kinetic parameters calculated by lattice physics codes such as TRITON and Polaris. In this study, extension of the database for the delayed neutron data (DND) is performed by exploring more delayed neutron experiments and adding additional ...
Majdi I. Radaideh, Tomasz Kozlowski, William A. Wieselquist, Matthew A. Jessee, Arkady Serikov   +4 more
wiley   +1 more source

A method for VVER fuel element cladding reliability prediction [PDF]

Ядерна фізика та енергетика, 2014
Considering a VVER-1000 fuel assembly averaged fuel element (FE), based on the accepted FE cladding damage limit value, the FE cladding failure probability was determined, thus the possibility of this reliability pre-diction by means of controlling the ...
S. M. Pelykh, M. V. Maksimov, M. V. Nikolsky   +2 more
doaj  

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology

EPJ Nuclear Sciences & Technologies, 2016
This paper shows basic features of different fuel assembly (FA) application for VVER-1000 in a closed fuel cycle based on REMIX-technology. This investigation shows how the change in the water–fuel ratio in the VVER FA affects on the fuel characteristics
Bobrov Evgenii, Alekseev Pavel, Chibinyaev Alexander, Teplov Pavel, Dudnikov Anatoliy   +4 more
doaj   +1 more source

Investigation of Irradiation Hardening and Effectiveness of Post-Irradiation Annealing on the Recovery of Tensile Properties of VVER-1000 Realistic Welds Irradiated in the LYRA-10 Experiment

Metals
Assessing the embrittlement and hardening of reactor pressure vessel steels is critical for the extension of the service lifetime of nuclear power plants.
M. Laot, Viviam Marques Pereira, T. Bakker, Elio d’Agata, Oliver Martin, M. Kolluri   +5 more
semanticscholar   +1 more source

Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis

Chemical Engineering &Technology, Volume 47, Issue 11, November 2024.
Conventional fluids used in fission‐based water‐cooled nuclear reactors have lower heat transfer coefficients and thermal conductivity, prompting researchers to explore high‐performance fluids to enhance heat transfer and prevent core meltdown during accidents. It is crucial to investigate fluids that can improve thermal hydraulic characteristics, such
Rehan Zubair Khalid, Mehmood Iqbal, Aitazaz Hassan, Syed Muhammad Haris, Atta Ullah   +4 more
wiley   +1 more source

Neutronic Investigation on Thorium Mox Fuel in Vver-1000 Reactor Assembly

Latvian Journal of Physics and Technical Sciences
The accumulation of plutonium produced by LWR operations causes public concern related to its radiotoxicity and proliferation issue. Therefore, there is some interest in developing various methods for consuming plutonium through plutonium incineration i ...
Zuhair, W. Luthfi, R. Dwijayanto, M.D. Isnaini, Suwoto   +4 more
semanticscholar   +1 more source

Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants

Energy Science &Engineering, Volume 12, Issue 11, Page 4894-4903, November 2024.
Exploring thermal flow dynamics in pressurized water reactors using hybrid graphene nanoplatelet coolants. Abstract This study investigates the impact of hybrid nanoparticles on the temperature of nuclear reactor coolant, with a focus on graphene nanoplatelet (GNP)‐based hybrid nanoparticles. Sixteen different hybrid nanofluids were analyzed, and their
Sinem Uzun, Yasin Genç, Adem Acır
wiley   +1 more source

Validation of the code package MCPV with continuous-energy data library [PDF]

Ядерна фізика та енергетика
The results of the validation of the code package MCPV for the calculation of radiation transport within VVER-1000 reactor type near-vessel space using a continuous-energy data library are presented.
О. M. Pugach, S. M. Pugach, V. L. Diemokhin, V. N. Bukanov, O. V. Grytsenko   +4 more
doaj   +1 more source