scholarly journals INFLUENCE OF THERMAL RATING AND BULK DENSITY ON IRRADIATION PERFORMANCE OF FUSED UO$sub 2$ TUBULAR FUEL ELEMENTS.

1966 ◽  
Author(s):  
G.R. Cole
Keyword(s):  
Bulk Density ◽  
Tubular Fuel ◽  
Irradiation Performance ◽  
Fuel Elements

Fabrication, Properties and Irradiation Performance of Molded Block Fuel Elements for HTGRs

2008 ◽  
Author(s):  
Milan F. Hrovat ◽  
Karl-H. Grosse ◽  
Richard Seemann
Keyword(s):  
Coated Particles ◽  
Cooling Channels ◽  
Block Form ◽  
Graphite Matrix ◽  
Demonstration Plant ◽  
Irradiation Performance ◽  
Fuel Elements ◽  
Monolithic Structure ◽  
Very High ◽  
Crystalline Graphite

The molded block fuel element (FE) also called monolith is a molded body, consisting of a substantially isotropic highly crystalline graphite matrix, fuel regions within the same matrix and cooling channels. The fuel regions contain the fuel in the form of coated particles which are well bonded to the remaining graphite matrix, so that both parts of the block form a monolithic structure. The monolith meets the requirements for the very high temperature reactors attaining helium outlet temperatures above 1000°C. To fabricate the molded blocks FE demonstration plant was erected and put into operation. The equipment worked without malfunction. The produced block FEs meet the specifications of GA machined block FEs. All specimens and block segments irradiated at temperature up to 1600°C and max. fast fluence E > 0, 1 MeV of 11×1021 n/cm2 show perfect behaviour without any damage.

Effects of Thickness of Zirconium Liner on Stress-Strain Characteristics of U10Mo Monolithic Plates

2013 ◽  
Author(s):  
Hakan Ozaltun ◽  
Robert M. Allen ◽  
You Sung Han
Keyword(s):  
Diffusion Barrier ◽  
Reactor Core ◽  
Stress Strain ◽  
Strain Behavior ◽  
Uranium Fuel ◽  
Plate Design ◽  
Enriched Uranium ◽  
Test Reactor ◽  
Irradiation Performance ◽  
Fuel Elements

The effects of the thickness of Zirconium liner on stress-strain behavior of monolithic fuel mini-plates during fabrication and irradiation processes were studied. Monolithic plate-type fuel elements is a new fuel form being developed for research and test reactors to achieve higher uranium densities which allows the use of low-enriched uranium fuel in reactor core. These fuel elements are comprised of a high density, low enrichment, U–Mo alloy based fuel foil encapsulated in a cladding material made of Aluminum. Early RERTR experiments indicated that the presence of an interaction layer between the fuel and cladding materials causes mechanical problems. To minimize the fuel/cladding interaction, employing a diffusion barrier between the cladding and the fuel materials was proposed. Current monolithic plate design employs a 0.025 mm thick, 99.8% pure annealed Zirconium diffusion barrier between the fuel foil (U10Mo) and the cladding materials (AL6061-O). To benchmark the irradiation performance, a number of plates were irradiated in the Advanced Test Reactor (ATR) with promising irradiation performance. To understand the effects of the thickness of the Zirconium diffusion barrier on the stress-strain behavior of the plates during fabrication, irradiation and shutdown stages, a representative plate from RERTR-12 experiments (Plate L1P7A0) was selected and simulated. Both fabrication and irradiation stages were considered. Simulations were repeated for various Zirconium thicknesses to understand the effects of the thickness of the diffusion barrier. Results of fabrication simulations indicated that Zirconium thickness has noticeable effects on foil’s stresses. Irradiation simulations revealed that the fabrication stresses of the foil would be relieved rapidly in the reactor. Results also showed that Zirconium thickness has little or no effects on irradiation and shutdown stresses.

EBR-II Metallic Driver Fuel—A Live Option

1981 ◽  
Vol 103 (4) ◽  
pp. 612-620 ◽  
Author(s):  
B. R. Seidel ◽  
L. C. Walters
Keyword(s):  
Power Systems ◽  
Chemical Interaction ◽  
High Reliability ◽  
Metallic Fuel ◽  
Close Coupling ◽  
Temperature Capability ◽  
Test Elements ◽  
Higher Temperature ◽  
Irradiation Performance ◽  
Fuel Elements

The exceptional performance of metallic driver fuel has been demonstrated by the irradiation of a large number of Experimental Breeder Reactor II (EBR-II) driver-fuel elements of uranium-5 wt percent fissium clad in austenitic stainless steel. High burnup with high reliability has been achieved by a close coupling of element design and materials selection. The irradiation performance has been improved by decreasing the fuel smear density, increasing the plenum volume, increasing the cladding thickness, and selecting a higher-strength, lower-swelling cladding alloy which exhibits less fuel-cladding chemical interaction. Quantification of reliability has allowed full utilization of the element lifetime. Lifetimes much greater than 10 at. percent could be achieved by a design change of the restrainer, which currently limits life. Use of U-Pu-Zr fuel alloy with current cladding material would provide higher-temperature capability, as demonstrated by test elements. Metallic fuel systems with their inherently superior breeding and irradiation performance are capable and attractive next-generation power systems.

Water-graphite reactors with tubular fuel elements

Atomic Energy ◽  
1996 ◽  
Vol 80 (5) ◽  
pp. 329-334
Author(s):  
V. V. Dolgov ◽  
L. A. Kochetkov ◽  
V. N. Sharapov
Keyword(s):  
Tubular Fuel ◽  
Fuel Elements

scholarly journals Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

2015 ◽  
Author(s):  
Jill Wright ◽  
Hakan Ozaltun
Keyword(s):  
High Performance ◽  
Mechanical Performance ◽  
Foil Thickness ◽  
Operational Variables ◽  
Total Magnitude ◽  
Irradiation Performance ◽  
Fuel Elements ◽  
Performance Research ◽  
Cladding Material ◽  
Plate Type

Monolithic plate-type fuel is a fuel form being developed for high performance research and test reactors to minimize the use of enriched material. These plate-type fuels consist of a high uranium density LEU foil contained within diffusion barriers and encapsulated within a cladding material. To benchmark this new design, effects of various geometrical and operational variables on irradiation performance have been evaluated. For this work, the effects of fuel foil centering on the thermo-mechanical performance of the mini-plates were studied. To evaluate these effects, a selected plate from RERTR-12 experiments, the Plate L1P756, was considered. The fuel foil was moved within the fuel plate to study the effects of the fuel centering on stress, strain and overall shape of the fuel elements. The thickness of the fuel foil, thickness of the Zr-liners and total thickness of the plate were held constant, except the centerline alignment of the fuel foil. For this, the position of the fuel foil was varied from the center position to a maximum offset corresponding to the minimum allowable aluminum cladding thickness of 0.1524 mm. Results for various offset cases were then compared to each other and to the ideal case of a centered fuel foil. Fabrication simulations indicated that the thermal expansion mismatch results in warping of the fuel plate during fabrication as the fuel plate is cooled from the HIP temperature when the fuel is not centered. Even if the model is constrained during cooling to simulate the rigid HIP can surrounding the fuel plate during cooling, warping is observed when the constraint is removed. Similarly, irradiation simulations revealed that the fuel offset causes virtually all irradiation-induced swelling to occur on the thin-cladding side of the plate. This is observed even for the smallest offset that was considered. The total magnitude of the swelling is approximately same for all offsets values.

Direct-flow scheme of reactor with smooth tubular fuel elements for maneuverable atomic power plant

1980 ◽  
Vol 48 (1) ◽  
pp. 8-12
Author(s):  
V. N. Smolin ◽  
V. I. Esikov ◽  
Yu. I. Mityaev ◽  
S. A. Vasil'ev
Keyword(s):  
Power Plant ◽  
Atomic Power Plant ◽  
Direct Flow ◽  
Flow Scheme ◽  
Tubular Fuel ◽  
Fuel Elements

Start-up and operation of channel-type uranium-graphite reactor with tubular fuel elements and nuclear steam superheating

1971 ◽  
Vol 30 (2) ◽  
pp. 163-170 ◽  
Author(s):  
P. I. Aleshchenkov ◽  
G. A. Zvereva ◽  
G. A. Kireev ◽  
G. D. Knyazeva ◽  
V. I. Kononov ◽  
...  
Keyword(s):  
Graphite Reactor ◽  
Start Up ◽  
Tubular Fuel ◽  
Fuel Elements ◽  
Steam Superheating ◽  
Channel Type
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