Results 61 to 70 of about 302 (158)

Title Investigation of the influence of various factors on the power of heat exchange by radiation

Trudy Odesskogo Politehničeskogo Universiteta, 2017
The issue of lack of knowledge of radiation heat transfer process has been repeatedly raised in various studies. Despite the fact that works on study of heat transfer by radiation covers a wide range of different industries, it should be noted the lack ...
Korolyov Alexander V. , Ishchenko Oleg P.   +1 more
doaj   +1 more source

Analysis of calculation of fuel rods for strength under transient and steady-state operating conditions

Nuclear Materials and Energy
The operating conditions are analyzed, mechanical characteristics are calculated pertaining to the 4-year cycle fuel rods of VVER-1000. The fuel rod strength characteristics are considered as applied to steady-state and transient conditions of reactor ...
Stepan Lys, Alexandr Kanyuka
doaj   +1 more source

Improving the accuracy of thermal power determination of VVER

Ядерна фізика та енергетика, 2019
In most algorithms for forming control signals, locks and protection of VVER, the value of the reactor’s thermal power (RTP) is used. This article is dedicated to the analysis of the problem of determining the RTP of VVER-1000.
V. I. Borysenko, D. V. Budyk, V. V. Goranchuk   +2 more
doaj   +1 more source

Synergies in VVER reactor long-term operation and aging: A comprehensive review of CAMIVVER, DELISA-LTO, and EVEREST projects

EPJ Nuclear Sciences & Technologies
This paper reviews the synergies between three Euratom projects–CAMIVVER, DELISA-LTO, and EVEREST–focusing on the long-term operation (LTO) and safety assessment of VVER reactors.
Hursin Mathieu, Perin Yann, Verrier Denis, Slugen Vladimir, Veternikova Jana Simeg   +4 more
doaj   +1 more source

PARCS/TRACE COUPLING METHODOLOGY FOR ROD EJECTION ON VVER 1000 REACTOR

Acta Polytechnica CTU Proceedings, 2016
The rod ejection (RE) is a design basis accident in accordance with NUREG-0800 and usually studied using point kinetics. In this paper a methodology and a 3D kinetic model is prepared (PARCS), coupled with a thermal hydraulic system code (TRACE) for ...
Marek Ruščák, Guido Mazzini
doaj   +1 more source

Vanquishing the computational cost of passive gamma emission tomography simulations leveraging physics-aware reduced order modeling. [PDF]

Sci Rep, 2023
Cavallini N, Ferretti R, Bostrom G, Croft S, Fassi A, Mercurio G, Nonneman S, Favalli A.   +7 more
europepmc   +1 more source

Investigation of thermal performance of aluminum nanoparticle coolant in vver-1000 reactor

, 2020
Nükleer güç reaktörlerinin güvenlik ve tasarım özellikleri incelenirken termal analizlerin önemi büyüktür. Bu çalışmada amaç, saf ve Al2O3 nano parçacık içeren soğutucu akışkanların VVER -1000 nükleer reaktör termal performansına etkisinin incelenmesidir.
UZUN, Sinem, GENÇ, Yasin, ACIR, Adem
openaire   +2 more sources

Localizing Perturbations in Pressurized Water Reactors Using One-Dimensional Deep Convolutional Neural Networks. [PDF]

Sensors (Basel), 2021
Pantera L, Stulík P, Vidal-Ferràndiz A, Carreño A, Ginestar D, Ioannou G, Tasakos T, Alexandridis G, Stafylopatis A.   +8 more
europepmc   +1 more source

Structural and Parametric Optimization of S-CO₂ Nuclear Power Plants. [PDF]

Entropy (Basel), 2021
Rogalev N, Rogalev A, Kindra V, Komarov I, Zlyvko O.   +4 more
europepmc   +1 more source

Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

EPJ Web of Conferences, 2016
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A., Tsofin V., Kochkin V., Panferov P., Timofeev A., Reshetnikov A., Makhotin D., Erak D., Voloschenko A.   +8 more
doaj   +1 more source