Solving the p-Laplacian on manifolds Troyanov, Marc
Proceedings of the American Mathematical Society,
02/2000, Letnik:
128, Številka:
2
Journal Article
Recenzirano
Odprti dostop
We prove in this paper that the equation \Delta _{p}u+h=0 on a p-hyperbolic manifold M has a solution with p-integrable gradient for any bounded measurable function h : M \to \mathbb R with compact ...support.
EdF’s idea of irradiating in Russian fast reactors fuel pins with recycled plutonium arose in February 2016 during a discussion with CEA of testing experimental FA in BN-600. EdF proposed to ...additionally irradiated several fuel pins fabricated using plutonium obtained after reprocessing of mixed fuel irradiated in PWR. In 2017, the studies with fabrication of full-scale FA were to expensive, so that proposals were developed for irradiating several tens of grams of UO
2
–PuO
2
in a laboratory facility in Atalante (CEA), using plutonium obtained during reprocessing of mixed fuel, as well as several ASTRID-type fuel pins in BN-600. The studies are to be conducted in three stages: small-scale irradiation in BOR-60, computational studies of the irradiation of 10 full-scale FA with recycled plutonium in BN-600, irradiation in BN-600 of one to five experimental ASTRID-type fuel pins with recycled plutonium. The technical problems of the specified experiments are discussed.
We define and study a natural weak metric on the Teichmüller space of the torus. A similar metric has been defined by W. Thurston on the Teichmüller space of higher genus surfaces and our definition ...is motivated by Thurston's definition. However, we shall see that in the case of the torus, this metric has a different behaviour than on higher genus surfaces.
We generalize the celebrated results of Bernhard Riemann and Gaston Darboux: we give necessary and sufficient conditions for a bilinear form to be flat. More precisely, we give explicit necessary and ...sufficient conditions for a tensor field of type (0,2) which is not necessary symmetric or skew-symmetric, and is possibly degenerate, to have constant entries in a local coordinate system.
Capacities in metric spaces Gol'dshtein, Vladimir; Troyanov, Marc
Integral equations and operator theory,
10/2002, Letnik:
44, Številka:
2
Journal Article
A thin wall tubular-type speciment of 4%Ti–4%Cr vanadium alloy was tested for creep under irradiation in BR-10 reactor at 713–723 K and at 8.6 × 10
18 n/m
2s fast neutron flux. A fluence at the end ...of the experiment have reached 5.8 × 10
25 n/m
2. Specimen deformation measurements were performed by a dynamometric method based on a stress relaxation control provided during irradiation under constant load applied. During the experiment 13 deformation curves were obtained for different stress levels ranged up to 165 MPa. At the same time the yield stress of the irradiated specimen was periodically determined. The irradiation creep rate has been found to be proportional to the stress up to 110–120 MPa with the module equal to 3.3 × 10
−12 dpa
−1Pa
−1. At higher streses, a creep process essentially accelerates. The results on VTiCr alloy are discussed in respect to data obtained for stainless steels in earlier BR-10 reactor experiments.
A special feature of the BREST-OD-300 reactor that is now being designed is that it employs a container-type heat-conducting fuel element with mixed uranium-plutonium mononitride fuel, a lead ...sublayer, and an expansion volume at the top to collect gaseous products. The fuel elements are arranged in a square array with a wide spacing and are spaced by laminated spacing lattices. The substantiation of the technical solutions adopted for the construction of the reactor fuel elements and fuel assemblies, specifically, the combined effect of the coolant and heat loads on the fuel-element cladding and the spacing lattices, led to the choice of the BOR-60 sodium-cooled fast research reactor as an experimental base and required the development and construction of an autonomous lead-cooled channel loaded into a cell through a passage in the rotatable plugs of the reactor. The channel was tested for two microruns with the BOR-60 reactor operating at 45 MW. The lead temperature at the fuel assembly entrance was 595C, the working temperature of the cladding was ,658C, the damaging dose was 6.5 displacements/atom, and the fuel burnup was 0.44% h.a. Analysis of the activity of the gas and the lead showed that the fuel elements are sealed. Post-reactor studies have been conducted since August 2002.
PDF
