scholarly journals Subcritical Measurements of Water-Moderated Highly Enriched Uranium Oxide MTR Type Fuel

2018 ◽  
Author(s):  
Anthony J. Nelson ◽  
Soon S. Kim ◽  
Jerome M. Verbeke ◽  
William J. Zywiec
Keyword(s):  
Uranium Oxide ◽  
Enriched Uranium ◽  
Type Fuel

Coupled Calculation on Fluid Structure Interaction in Plate-Type Fuel Element

2018 ◽  
Author(s):  
Yiqi Yu ◽  
Elia Merzari ◽  
Jerome Solberg
Keyword(s):  
Fuel Element ◽  
Fluid Structure Interaction ◽  
Initial Step ◽  
University Of Missouri ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Coupled Calculation ◽  
Enriched Uranium ◽  
Type Fuel ◽  
Plate Type

In nuclear reactors that use plate-type fuel, the fuel plates are thermally managed with coolant flowing through channels between the plates. Depending on the flow rates and sizes of the fluid channels, the hydraulic forces exerted on a plate can be quite large. Currently, there is a worldwide effort to convert research reactors that use highly enriched uranium (HEU) fuel, some of which are plate-type, to low-enriched uranium (LEU). Because of the proposed changes to the fuel structure and thickness, a need exists to characterize the potential for flow-induced deflection of the LEU fuel plates. In this study, as an initial step, calculations of Fluid-Structure Interaction (FSI) for a flat aluminum plate separating two parallel rectangular channels are performed using the commercial code STAR-CCM+ and the integrated multi-physics code SHARP, developed under the Nuclear Energy Advanced Modeling and Simulation program. SHARP contains the high-fidelity single physics packages Diablo and Nek5000, both highly scalable and extensively validated. In this work, verification studies are performed to assess the results from both STAR-CCM+ and SHARP. The predicted deflections of the plate agree well with each other as well as exhibiting good agreement with simulations performed by the University of Missouri utilizing STAR-CCM+ coupled with the commercial structural mechanics code ABAQUS. The study provides a solid basis for FSI modeling capability for plate-type fuel element with SHARP.

Improved-Trapped Magnetic Fields in Top Seeded Melt Grown YBCO Superconductor Doped with Depleted and Enriched Uranium Oxide

2003 ◽  
Vol 426-432 ◽  
pp. 3499-3504 ◽  
Author(s):  
D.A. Cardwell ◽  
N. Hari Babu ◽  
M. Kambara ◽  
Y.H. Shi ◽  
C.D. Tarrant ◽  
...  
Keyword(s):  
Magnetic Fields ◽  
Uranium Oxide ◽  
Ybco Superconductor ◽  
Enriched Uranium

Uranium Workshops Dismantling and Criticality Control

2011 ◽  
Author(s):  
Pierre Lisbonne ◽  
Julie Rosello
Keyword(s):  
Risk Management ◽  
Uranium Oxide ◽  
Chemical Processes ◽  
Process Equipment ◽  
Fissile Material ◽  
Nuclear Facility ◽  
Southern France ◽  
Management Procedures ◽  
Enriched Uranium

Within the CEA at Cadarache Research Center located in southern France, the ATUE, standing for Ateliers de Traitement de l’Uranium Enrichi (Enriched Uranium Treatment Workshops), is a nuclear facility started in 1965 and shut down in 1995. Various chemical processes were in operation in the ATUE in order to product enriched uranium oxide intended for fast breeders and naval propulsion reactors. According to the mass of fissile material, the most contaminated process equipment has already been dismantled under criticality risk management procedures. Cleanup of the building and dismantling of the remaining equipment, such as ventilation and electricity network, are now in progress without any constraint regarding criticality, thanks to in-situ measurement and calculations. Criticality management and how we finally proved the risk was over, as well as the strategy under French rules for final decommissioning of the facility leading to “brown field” will be presented.

Transient Behavior of Low Enriched Uranium Silicide Plate-Type Fuel for Research Reactors during Reactivity Initiated Accident Conditions

1993 ◽  
Vol 30 (8) ◽  
pp. 741-751 ◽  
Author(s):  
Kazuaki YANAGISAWA ◽  
Toshio FUJURO ◽  
Oichiro HORIKI ◽  
Kazuhiko SOYAMA ◽  
Hiroki ICHIKAWA ◽  
...  
Keyword(s):  
Transient Behavior ◽  
Research Reactors ◽  
Enriched Uranium ◽  
Accident Conditions ◽  
Type Fuel ◽  
Plate Type ◽  
Uranium Silicide

scholarly journals Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library

2021 ◽  
Vol 2021 ◽  
pp. 1-9
Author(s):  
Sonia M. Reda ◽  
Ibrahim M. Gomaa ◽  
Ibrahim I. Bashter ◽  
Esmat A. Amin
Keyword(s):  
Uranium Oxide ◽  
Delayed Neutron ◽  
Reactor Operation ◽  
Plutonium Isotopes ◽  
The Core ◽  
Reactivity Coefficients ◽  
Design Values ◽  
Enriched Uranium ◽  
Neutronic Performance ◽  
Lower Production

In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER-1000 reactor was discussed. The reference core was initially filled with enriched uranium oxide fuel and then fueled with uranium-thorium fuel. The calculations determine the delayed neutron fraction βeff, the temperature reactivity coefficients, the fuel consumption, and the production of the transuranic elements during reactor operation. βeff and the Doppler coefficient (DC) are found to be in agreement with the design values. It is found that the core loaded with uranium and thorium has lower delayed neutron fraction than the uranium oxide core. The moderator temperature coefficients of the uranium-thorium core are found to be higher than those of the uranium core. Results indicated that thorium has lower production of minor actinides (MAs) and transuranic elements (mainly plutonium isotopes) compared with the relatively large amounts produced from the uranium-based fuel UO2.

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