Results 221 to 230 of about 3,448 (263)

The application of UWB1 nuclear fuel depletion code on a CANDU fuel bundle

Progress in Nuclear Energy, 2016
Abstract A computer code (UWB1) that is applicable for both light and heavy water reactor fuel types is being developed at the University of West Bohemia. CANDU fuel geometry was investigated in this paper. Fuel depletion with UWB1 code was performed and compared to other depletion codes. A feasibility study on the use of burnable absorbers in CANDU
M. Lovecký, R. Škoda, M.S. Hussein, J.J. Song, P.K. Chan   +4 more
openaire   +1 more source

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Volume 3: Fluid Structure Interaction; High Pressure Technology, 2021
Abstract Fuel bundles in nuclear power plants are subjected to severe operation conditions, such as highly turbulent coolant flow, high temperatures and excessive irradiation doses. These irradiation doses affect the microstructure of the material in terms of segregation and precipitation in addition to swelling.
Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy   +3 more
openaire   +1 more source

Vibration of nuclear fuel bundles

Nuclear Engineering and Design, 1975
Abstract Several mathematical models have been proposed for calculating fuel rod responses in axial flows based on a single rod consideration. The spacing between fuel rods in liquid metal fast breeder reactors (LMFBRs) is small; hence fuel rods will interact with one another due to fluid coupling.
openaire   +1 more source

Effective heat conductivity of fuel element bundles and steam generator tube bundles

Journal of Nuclear Materials, 2008
Effective heat conductivity of rod and tube bundles is one of thermophysical properties necessary for calculation of thermo hydraulic characteristics of heat producing devices, heat exchange devices and steam generators. This report introduces results of mathematical modeling of effective heat conductivity of transversally anisotropic rod bundles in ...
V. Fedotovsky, A. Orlov
openaire   +1 more source

Simulation of motion-dependent fluid forces in fuel bundles

Nuclear Engineering and Design, 2020
Abstract Fuel bundles in CANDU (Canada Deuterium Uranium) reactors are subject to axial flow-induced vibrations. This could result in fretting wear in the inner surface of the pressure tube or in the integrity of the bundles being compromised. Various fluid excitations can affect the dynamic response of the fuel bundle.
Osama Elbanhawy, Marwan Hassan, Atef Mohany   +2 more
openaire   +1 more source

HLM Fuel Pin Bundle Characterization in CIRCE Pool Facility

Volume 2B: Thermal Hydraulics, 2014
Since the Lead-cooled Fast Reactor (LFR) has been conceptualized in the frame of GEN IV International Forum (GIF), ENEA is strongly involved on the HLM technology development. Currently ENEA has implemented large competencies and capabilities in the field of HLM thermal-hydraulic, coolant technology, material for high temperature ...
MARTELLI, DANIELE, Tarantino M., Di Piazza I., FORGIONE, NICOLA, Agostini P., Coccoluto G.   +5 more
openaire   +1 more source

Bundled Slash: A Potential New Biomass Resource for Fuels and Chemicals

Applied Biochemistry and Biotechnology, 2007
Postharvest residues for southern pine species have not previously been quantified to compare volumes produced from both thinnings and clearcut volumes. A John Deere 1490 Slash Bundler bundled postharvest residues following a first thinning of a 14-year-old stand, a second thinning of a 25-year-old stand, and a clearcut of a naturally regenerated ...
Philip H, Steele, Brian K, Mitchell, Jerome E, Cooper, S, Arora   +3 more
openaire   +2 more sources

A comprehensive in-pile test of PWR fuel bundle

Journal of Nuclear Materials, 1991
Abstract An in-pile test of PWR fuel bundle has been conducted in HWRR at IAE of China. This paper describes the structure of the test bundle (3 × 3−2), fabrication process and quality control of the fuel rod, irradiation conditions and the main Post Irradiation Examination (PIE) results.
Rixin Kang, Shucheng Zhang, Dianshan Chen   +2 more
openaire   +1 more source

Modelling of fuel bundle vibration and the associated fretting wear in a CANDU fuel channel

Nuclear Engineering and Design, 2013
Abstract In this paper a numerical model is developed to predict the vibration response of a CANDU 1 fuel bundle and the associated fretting wear in the surrounding pressure tube. Two excitation mechanisms are considered in this model: turbulence-induced excitation caused by coolant flow inside the fuel channel, and seismic excitation.
A. Mohany, M. Hassan
openaire   +1 more source

Numerical simulation of flows in tight-lattice fuel bundles

Nuclear Engineering and Design, 2008
Abstract The flow in tight rod bundles is characterized by long-term, large-scale coherent patterns in the stream-wise direction. In the present work, the issue of simulating these structures through unsteady CFD simulations employing periodic boundary conditions in the stream-wise direction, will be addressed.
E. Merzari, H. Ninokata, E. Baglietto
openaire   +1 more source