Results 231 to 240 of about 3,448 (263)

Critical velocity of fluidelastic vibration in a nuclear fuel bundle

KSME International Journal, 2000
In the core of the nuclear power plant of PWR, several cases of fuel failure by unknown causes have been experienced for various fuel types. From the common features of the failure pattern, failure lead time, flow conditions, and flow induced vibration characteristics in nuclear fuel bundles, it is deduced that the fretting wear failure of the fuel rod
Sang Nyung Kim, Sung Yup Jung
openaire   +1 more source

Flow Dynamics in a Fuel Bundle With a Particle Bed

Volume 6: Thermal-Hydraulics and Safety Analysis
Abstract The pressure reduction in the RCS and temperature excursion of the cladding during a postulated loss-of-coolant accident (LOCA) can lead to cladding rupture. Fuel fragmentation can occur at any burnup, but the fuel fragment sizes decrease with increasing burnup, thereby increasing the potential for relocation and dispersal via ...
Scott C. Franz, Gordon J. Wissinger
openaire   +1 more source

CFD and DNS methodologies development for fuel bundle simulations

Nuclear Engineering and Design, 2006
Development and application of computational fluid dynamics (CFD) and direct numerical simulation (DNS) approaches to the reproduction of coolant flow inside nuclear fuel bundles are discussed, focusing on the advantages and limitations of the different methodologies and on their synergetic potential.
E. Baglietto, H. Ninokata, T. Misawa
openaire   +1 more source

Filler metals for containers holding irradiated fuel bundles

Metals Technology, 1982
Abstract One of the procedures being considered for the disposal of Canada deuterium uranium (CANDU) irradiated fuel bundles is to place the bundles in containers, fill the containers with metal, and place them underground. This investigation deals with the selection of the filler metal with particular reference to the reaction rate with, and bonding ...
P. M. Mathew, F. Weinberg, J. S. Nadeau, A. C. D. Chaklader   +3 more
openaire   +1 more source

Reconstruction of Fuel Pin Bundles by a Maximum Entropy Method

IEEE Transactions on Nuclear Science, 1979
Tomographic reconstructions from several views of a 37-pin reactor fuel core bundle are presented. A maximum entropy method is used to produce reconstructions from three, six, and eighteen views of a fuel bundle with voids and partial voids.
openaire   +1 more source

LES of heated fuel bundle arranged into triangular array

2011
A rod bundle is a key constitutive element of a wide range of nuclear reactor designs. It is composed by a set of long thin rods containing the nuclear fuel and fluid-flow between them and generally parallel to the rods. As experiments in a such densely packed geometries are difficult, thermal-hydraulics simulations are valuable to study heat transfer,
S. Rolfo, J. C. Uribe, D. Laurence
openaire   +1 more source

A subchannel analysis of DUPIC fuel bundle for the CANDU reactor

Annals of Nuclear Energy, 1999
Abstract Thermal characteristics of the reference DUPIC fuel has been studied for its feasibility of loading in the CANDU reactor. Half of the DUPIC fuel bundle has been modeled for a subchannel analysis of the ASSERT-IV Code which was developed by AECL.
openaire   +1 more source

Numerical investigations of the effect of operation conditions on the heat transfer of the supercritical water in the Canadian SCWR fuel bundle

Journal of Supercritical Fluids, 2022
Huirui Han
exaly  

BWR Fuel Bundle Optimization Based on Three-Dimensional Fuel Rods

Transactions of the American Nuclear Society - Volume 121, 2019
B. Andersen, J. Hou, D. Kropaczek
openaire   +1 more source

Bundle geometry design influence on fuel burnup and performances in a CANDU reactor

Annals of Nuclear Energy, 2020
Iosif Prodea
exaly