Results 131 to 140 of about 821 (181)

Induction cladding of alloys and metal-matrix composite coatings: A review. [PDF]

Heliyon
Yu J, Zhang S.
europepmc   +1 more source

Tensile properties of the neutron irradiated HT-9 ACO-3 duct. [PDF]

Sci Rep
Saleh TA, Eftink BP, Romero TJ, Piedmont D, Stubbins JF, Toloczko M, Maloy SA.   +6 more
europepmc   +1 more source

Fundamental study of fuel-cladding chemical interaction in oxide fuel elements of nuclear reactors

, 1989
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Effect of fuel and cladding eccentricity, cladding ovality, and fuel-pellet chipping on the temperature field in a fuel element

Soviet Atomic Energy, 1989
A S Shcheglov
exaly   +2 more sources

Cladding Thickness of Fuel Elements by X-rays

Advances in X-ray Analysis, 1958
AbstractThe paper is based on a feasibility study to determine the suitability of various techniques for the non-destructive measurement of cladding thickness on uranium fuel elements. The techniques studied were: 1—the attentuation of the characteristic X-ray fluorescence from the uranium base metal by the cladding material, and 2—Compton scattering ...
Beverley James Lowe, Payson D. Sierer, Robert B. Ogilvie   +2 more
openaire   +1 more source

Irradiation enhanced creep in LMFBR fuel element cladding

Journal of Nuclear Materials, 1977
Abstract Rate changes observed in irradiation enhanced creep and swelling in stainless steel cladding are ascribed to the precipitation of carbide. Empirical equations modified according to precipitation kinetics are consistent with results from fuel element irradiation and in particular describe the “second peak” phenomenon.
Gerard L. HOFMAN, Jacques TRUFFERT, Jean-Michel DuPOUY   +2 more
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Thermal shock in a nuclear fuel element with cladding

Nuclear Engineering and Design, 1980
Abstract The object of the present paper is to look into the evolution of thermoelastic state in a nuclear pin with cladding, when a step-variation occurs in coolant temperature. For both fuel and cladding the transient stress components are obtained: they must be added to the steady stress components in the case of step-decrease ( ΔT ΔT > 0 ...
CARPINTERI, Alberto, E. LORENZINI
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Physicochemical interaction of oxide fuel with the cladding of the fuel elements of A fast reactor

Soviet Atomic Energy, 1984
The investigations of fuel elements with mixed oxide fuel, used in BOR-60, revealed four types of corrosion damage to OKh16N15M3B steel cladding due to the action of fission products. It was shown that the general corrosion develops as a result of the interaction of the cladding with cesium with an oxygen potential created by the mixed oxide fuel ...
V. A. Tsykanov, E. F. Davydov, E. P. Klochkov, V. K. Shamardin, V. N. Golovanov, F. N. Kryukov   +5 more
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Azimuthal temperature variation in the cladding of PWR fuel elements

Nuclear Engineering and Design, 1984
Abstract This paper is concerned with the prediction of the azimuthal temperature distribution in the cladding of the fuel elements of a pressurized water reactor (PWR), in the event of a loss of coolant accident (LOCA). It is assumed that ballooning of the fuel elements results in local restrictions of flow area as the cladding of adjacent rods ...
H. Barrow, A.K.A. Hassan
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Particulars of the Effect of the Internal Medium of a Fuel Element in High-Burnup Fuel on the Corrosion Cracking of Fuel-Element Cladding under Stress

Atomic Energy, 2014
The mechanism of the reduction of iodine partial pressure in the presence of oxygen is examined. Analysis of computational and experimental studies shows that in fuel elements with high fuel burnup the concentration of iodine beneath the cladding decreases more than 100-fold in connection with an increase in the partial pressure of oxygen entering the ...
Kuznetsov V I, Novikov V V
exaly   +2 more sources