Results 21 to 30 of about 2,554,621 (223)

Preliminary Analysis of the Cladding Mechanical Behavior of a Nuclear Superheat Boiling Water Reactor [PDF]

International Journal of Advanced Design and Manufacturing Technology, 2018
In the present study, investigation of mechanical behaviour of the fuel cladding material for a nuclear superheat Boiling Water Reactor with annular fuel rods, is carried out.
Majid Bahonar, Gholamreza Jahanfarnia, Morteza Gharib   +2 more
doaj  

CALCULATION OF NUCLEAR FUEL CLADDING INTERNAL COATING THICKNESS FOR EMERGENCY RESISTANT NUCLEAR FUEL ELEMENT

Известия Томского политехнического университета: Инжиниринг георесурсов, 2023
Link for citation: Rofida Hamad Khalifa Hamad, Nikitenkov N.N., Kudiyarov V.N. Calculation of nuclear fuel cladding internal coating thickness for emergency resistant nuclear fuel element. Bulletin of the Tomsk Polytechnic University.
Hamad Khalifa Hamad Rofida, Nikolai N. Nikitenkov, Viktor N. Kudiyarov   +2 more
doaj   +1 more source

Investigation of the influence of the fuel element design parameter on the VVER-1000 reactor axial power peaking factor [PDF]

Nuclear Energy and Technology, 2023
The paper presents the results of a numerical study into the efficiency of the fuel element operation in the pressurized water reactor (VVER) core filled with uranium dioxide (UO2) pellets. The investigation results were obtained from a three-dimensional
Vladimir A. Gorbunov, Svetlana S. Teplyakova, Nikita A. Lonshakov, Sergey G. Andrianov, Pavel A. Mineev   +4 more
doaj   +3 more sources

EFFECT OF Al, Zr AND Mo ON CORROSION RESISTANCE OF AlXCrFeNiMo AND AlXCrFeNiZr (X=1, 1.2 AND 1.4) AS FUEL CLADDING MATERIALS

Urania, 2022
EFFECT OF Al, Zr AND Mo ON CORROSION RESISTANCE OF AlXCrFeNiMo AND AlXCrFeNiZr (X=1, 1.2 AND 1.4) AS FUEL CLADDING MATERIALS. The high entropy alloy of AlxCrFeNiM (with x = 1, 1,2 and 1,4; M = Mo and Zr) was successfully synthesized using powder ...
Teguh Firmansyah, Bonita Dilasari, Jan Setiawan, Djoko Hadi Prajitno   +3 more
doaj   +1 more source

Effect of the fuel element bundle statistical characteristics on the evaluation of temperature in the sodium-cooled fast-neutron reactor core

Nuclear Energy and Technology, 2015
Different fuel element bundle models used to calculate the coolant and fuel cladding temperatures inside fuel assemblies have been analyzed as applied to sodium-cooled fast-neutron reactors. The drawbacks of the existing models have been identified.
B.B. Tikhomirov, V.M. Poplavsky
doaj   +1 more source

Multi-element fiber for space-division multiplexing

, 2013
A novel approach of using multi-element fiber (MEF) technology in space-division multiplexing (SDM) systems is presented. This paper reviews the progress in fabrication and characterization of MEF based both ultra-low crosstalk transmission and amplifier
V. J. F. Rancaño, May-Smith, T.C., Petropoulos, P., Jain, S., Richardson, D.J., T. C. May-Smith, S. Jain, J. K. Sahu, D. J. Richardson, P. Petropoulos, Sahu, J.K., Rancaño, V.J.F., A. Webb, Webb, A.   +13 more
core   +1 more source

Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

Applied Sciences, 2021
Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors. Usually, it is in service for a long time under the effects of neutron radiation with high temperature and high pressure, which results in thermomechanical ...
Hui Zhao, Chong Yang, Dongxu Guo, Lu Wu, Jianjun Mao, Rongjian Pan, Jiantao Qin, Baodong Shi   +7 more
doaj   +1 more source

Cladding-pumped Raman fiber with a W-type core designed for power scaling

, 2009
We design a cladding-pumped fiber Raman amplifier with a wavelength-filtering W-type core for the suppression of the 2nd-order Raman Stokes.
Nilsson, J., Ji, J., Codemard, C.A.
core   +2 more sources

Design of multiprobe for fuel-elements cladding eddy current testing [PDF]

Journal of Physics: Conference Series, 2020
Abstract This article presents a study of the eddy current flaw detector (ECFD) numeric model in order to choose the necessary parameters for zirconium pipes control. As a result of mathematical modeling, the multiprobe ECFD was designed and the eddy flaw control conditions were found.
A S Krukov, E G Shchukis, N P Kodak, V P Lunin   +3 more
openaire   +1 more source

Model for calculating the temperature in the fuel rods of the fa-x fuel assembly produced for subcritical instillation and reactor wwr-m

Trudy Odesskogo Politehničeskogo Universiteta, 2020
The TVS-X fuel rod model designed by NSC KIPT as an alternative fuel for subcritical assembly (SCA, KIPT, Kharkov) and research reactor (WWR-M, INR, Kiev) is described.
Ігор Олександрович Чернов, Антон Володимирович Куштим   +1 more
doaj   +5 more sources