Results 61 to 70 of about 278 (148)

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
openaire   +2 more sources

Research Progress of Steels for Nuclear Reactor Pressure Vessels. [PDF]

Materials (Basel), 2022
Zhou L, Dai J, Li Y, Dai X, Xie C, Li L, Chen L.   +6 more
europepmc   +1 more source

Obtaining an Equiaxed Ultrafine-Grained State of the Longlength Bulk Zirconium Alloy Bars by Extralarge Shear Deformations with a Vortex Metal Flow. [PDF]

Materials (Basel), 2023
Arbuz A, Kawalek A, Ozhmegov K, Panin E, Magzhanov M, Lutchenko N, Yurchenko V.   +6 more
europepmc   +1 more source

Development of methods and means to improve environmental, radiation and industrial safety of NPPs with WWER-1200

Глобальная ядерная безопасность
The introduction provides an overview of scientific research on the sources of generation, characteristics and classification of infrasound. It is noted that infrasound has a number of features related to the low oscillation frequency of the elastic ...
K. N. Proskuryakov, M. S. Khvostova
doaj   +1 more source

Bayesian Activity Estimation and Uncertainty Quantification of Spent Nuclear Fuel Using Passive Gamma Emission Tomography. [PDF]

J Imaging, 2021
Eldaly AK, Fang M, Di Fulvio A, McLaughlin S, Davies ME, Altmann Y, Wiaux Y.   +6 more
europepmc   +1 more source

Statistical Characterization of Strain-Controlled Low-Cycle Fatigue Behavior of Structural Steels and Aluminium Material. [PDF]

Materials (Basel), 2022
Bazaras Ž, Lukoševičius V.
europepmc   +1 more source

Stress intensity factors for through clad and underclad defects in a WWER type reactor pressure vessel in pressurised thermal shock analysis

Fracture and Structural Integrity
This study develops stress intensity factor (SIF) solutions for cladded WWER reactor pressure vessel nozzles subjected to pressurised thermal shock loading.
Vitalii Antonchenko, Yaroslav Dubyk, Volodymyr Iasnii   +2 more
doaj   +1 more source

Characterization of Simulated Liquid Radioactive Waste in a New Type of Cement Mixture. [PDF]

ACS Omega, 2022
Fabian M, Tolnai I, Kis Z, Szilagyi V.
europepmc   +1 more source

Development of a Neutronic Model of the WWER-1000 Reactor Facility Core

Eurasian Journal of Physics and Functional Materials
A neutronic model of the WWER-1000 reactor has been developed. The reactor block of the B-320 series, which is the most common among NPPs with the WWER type reactors, was selected for the modeling. The modeling was performed using the MCNP6 software.
Darkhan M. Seken, Artur S. Surayev, Ruslan A. Irkimbekov, Galina A. Vityuk , Nurzhan Y. Mukhamedov , Olzhas M. Zhanbolatov , Vladimir A. Vityuk   +6 more
doaj   +1 more source

The Influence of Zeolite (Sokyrnytsya Deposit) on the Physical and Chemical Resistance of a Magnesium Potassium Phosphate Compound for the Immobilization of High-Level Waste. [PDF]

Molecules, 2019
Kulikova SA, Vinokurov SE.
europepmc   +1 more source