Results 31 to 40 of about 10,588 (115)

Numerical Investigation of Conjugated Heat Transfer of the Plate-Type Fuel Assembly in the Research Reactor

Frontiers in Energy Research, 2021
In nuclear reactors, the research of conjugated heat transfer between the fuel and coolant in the fuel assembly is fundamental for improving the safety, reliability and economy.
Quan Li, Qiang Ma, Yuanming Li, Ping Chen, Chao Ma, Bo Zhao, Hao Chen   +6 more
doaj   +1 more source

Modelling and modal properties of nuclear fuel assembly

Applied and Computational Mechanics, 2011
The paper deals with the modelling and modal analysis of the hexagonal type nuclear fuel assembly. This very complicated mechanical system is created from the many beam type components shaped into spacer grids. The cyclic and central symmetry of the fuel
Zeman V., Hlaváč Z.
doaj  

Numerical Simulation of Pressure Loss and Heat Transfer in Road Bundle Fuel Assembly with Spacer Grids [PDF]

مجله علوم و فنون هسته‌ای, 2013
The spacer grids in nuclear fuel assembly are one of the equipments that affect the fluid flow distribution with the creation of turbulence and driven fluid flow in a sub-channel. In the present paper, the fuel bundle in the VVER-440 nuclear reactor that
M Asgari, M Talebi, M. R Abdi
doaj  

The solid angle subtended by a collimated detector and a nuclear fuel assembly [PDF]

Nuclear Technology and Radiation Protection, 2017
A Monte Carlo procedure is presented to calculate the solid angle subtended between a HPGe collimated detector and a PWR 17 x 17 fuel assembly.
Nicolaou Georgios
doaj   +1 more source

Development of numerical models for Monte Carlo simulations of Th-Pb fuel assembly

E3S Web of Conferences, 2017
The thorium-uranium fuel cycle is a promising alternative against uranium-plutonium fuel cycle, but it demands many advanced research before starting its industrial application in commercial nuclear reactors.
Oettingen Mikołaj
doaj   +1 more source

Prediction of the nuclear fuel rod abrasion

Applied and Computational Mechanics, 2013
The paper is focused on calculation of the friction forces work in the contact of nuclear fuel rods with fuel assembly spacer grid cells. This friction work is deciding factor for the prediction of the fuel rod coating abrasion.
Zeman V., Hlaváč Z.
doaj  

Refinement of Finite Element Method Analysis Model of Pressurized Water Reactor Nuclear Fuel Spacer Grid Based on Experimental Data

Energies
A Finite Element Method (FEM) analysis of the nuclear fuel spacer grid was conducted to assess the strength of components for the safety of nuclear power plants.
Minhee Kim, Ihn Namgung
doaj   +1 more source

Estimation of the nuclear fuel assembly eigenfrequencies in the probability sense

Applied and Computational Mechanics, 2014
The paper deals with upper and lower limits estimation of the nuclear fuel assembly eigenfrequencies, whose design and operation parameters are random variables.
Zeman V., Hlaváč Z.
doaj  

Comparison of ENDF/B-VII.1 and JEFF-3.2 in VVER-1000 operational data calculation

EPJ Web of Conferences, 2017
Safe operation of a nuclear reactor requires an extensive calculational support. Operational data are determined by full-core calculations during the design phase of a fuel loading.
Frybort Jan
doaj   +1 more source

Seismic response of nuclear fuel assembly

Applied and Computational Mechanics, 2014
The paper deals with mathematical modelling and computer simulation of the seismic response of fuel assembly components. The seismic response is investigated by numerical integration method in time domain.
Hlaváč Z., Zeman V.
doaj