Recovery of Enriched Uranium from Uranium Dioxide—Stainless Steel Fuel Elements by Solvent Extraction

1959 ◽  
Vol 51 (1) ◽  
pp. 23-26 ◽  
Author(s):  
J. R. Flanary ◽  
J. H. Goode
Keyword(s):  
Stainless Steel ◽  
Solvent Extraction ◽  
Uranium Dioxide ◽  
Enriched Uranium ◽  
Fuel Elements

scholarly journals A proposal for a new U-D2O criticality benchmark: RB reactor core 39/1978

2012 ◽  
Vol 27 (1) ◽  
pp. 75-83
Author(s):  
Milan Pesic
Keyword(s):  
Heavy Water ◽  
Uranium Dioxide ◽  
Reactor Core ◽  
Nuclear Fission ◽  
Natural Uranium ◽  
Single Type ◽  
Uranium Metal ◽  
The Core ◽  
Enriched Uranium ◽  
Fuel Elements

In 1958, the experimental RB reactor was designed as a heavy water critical assembly with natural uranium metal rods. It was the first nuclear fission critical facility at the Boris Kidric (now Vinca) Institute of Nuclear Sciences in the former Yugoslavia. The first non-reflected, unshielded core was assembled in an aluminium tank, at a distance of around 4 m from all adjacent surfaces, so as to achieve as low as possible neutron back reflection to the core. The 2% enriched uranium metal and 80% enriched uranium dioxide (dispersed in aluminum) fuel elements (known as slugs) were obtained from the USSR in 1960 and 1976, respectively. The so-called ?clean? cores of the RB reactor were assembled from a single type of fuel elements. The ?mixed? cores of the RB reactor, assembled from two or three types of different fuel elements, were also positioned in heavy water. Both types of cores can be composed as square lattices with different pitches, covering a range of 7 cm to 24 cm. A radial heavy water reflector of various thicknesses usually surrounds the cores. Up to 2006, four sets of clean cores (44 core configurations) have been accepted as criticality benchmarks and included into the OECD ICSBEP Handbook. The RB mixed core 39/1978 was made of 31 natural uranium metal rods positioned in heavy water, in a lattice with a pitch of 8?2 cm and 78

scholarly journals THE FABRICATION OF STAINLESS STEEL-URANIUM DIOXIDE FUEL ELEMENTS

1954 ◽  
Author(s):  
J.R. Keeler ◽  
D.L. Keller ◽  
L.J. Cuddy
Keyword(s):  
Stainless Steel ◽  
Uranium Dioxide ◽  
Fuel Elements

Characterisation of Enriched Uranium Dioxide Particles from a Uranium Handling Facility

1998 ◽  
Vol 79 (1) ◽  
pp. 57-62 ◽  
Author(s):  
M.D. Hoover ◽  
G.J. Newton ◽  
R.A. Guilmette ◽  
R.J. Howard ◽  
R.N. Ortiz ◽  
...  
Keyword(s):  
Uranium Dioxide ◽  
Enriched Uranium

scholarly journals DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS

1959 ◽  
Author(s):  
S.J. Paprocki ◽  
D.L. Keller ◽  
G.W. Cunningham ◽  
A.K. Jr. Foulds
Keyword(s):  
Stainless Steel ◽  
Dispersion Fuel ◽  
Uranium Nitride ◽  
Fuel Elements

scholarly journals Numerical investigations of stainless steel melt motions on the surface of uranium dioxide

2019 ◽  
Vol 196 ◽  
pp. 00005 ◽  
Author(s):  
Eduard V. Usov ◽  
Pavel D. Lobanov ◽  
Ilya A. Klimonov ◽  
Alexander E. Kutlimetov ◽  
Anton A. Butov ◽  
...  
Keyword(s):  
Stainless Steel ◽  
Uranium Dioxide ◽  
Momentum Conservation ◽  
Mass Energy ◽  
Numerical Investigations ◽  
Fuel Rod ◽  
The Core ◽  
Fuel Pin ◽  
Energy And Momentum ◽  
Coolant Velocity

The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.

Design of U3Si2-Al Plate-Type Fuel Element for China Advanced Research Reactor

2010 ◽  
Author(s):  
Aimin Zhang ◽  
Yalun Kang
Keyword(s):  
Fuel Element ◽  
Neutron Flux ◽  
Research Reactor ◽  
High Heat ◽  
Reactor Power ◽  
High Heat Flux ◽  
Water Tank ◽  
Enriched Uranium ◽  
Fuel Elements ◽  
Plate Type

China Advanced Research Reactor (CARR), which will be critical in China Institute of Atomic Energy (CIAE) in 2010, is a multipurpose, high neutron flux and tank-type (inverse neutron trap) reactor with compact core. Its nominal reactor power is 60MW and the maximum thermal neutron flux is about 8.0×1014n/cm2·s in heavy water tank. It has a cylindrical core having a diameter of about 450mm and a height of 850mm. The CARR’s core consists of seventeen plate-type standard fuel elements and four follower fuel elements, initially loaded with 10.97 kg of 235U. The fuel element has been designed with U3S2-Al dispersion containing 235U of (19.75±0.20)wt.% low enriched uranium (LEU) and having a density of 4.3gU/cm3. The aluminum alloy is used as the cladding. There are twenty-one and seventeen fuel plates in the standard and follower fuel element, respectively. There are specific requirements for design of the fuel element and strict limitation for the operation parameters due to the high heat flux and high velocity of coolant in CARR. Irradiation test of fuel element had been carried out at fuel element power of 3.1±20%MW at Russia MIR reactor. Average burnup of fuel element is up to 40%. This paper deals with the detailed design of fuel element for CARR, out-pile and in-pile test projects, including selection of fuel and structure material, description of element structure, miniplates and fuel element irradiation experiment, measurement of properties of fuel plate, fabrication of fuel element and test results.

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