Results 181 to 190 of about 2,554,621 (223)

Transient temperature distribution in the clad of a cylindrical fuel element

Nuclear Engineering and Design, 1967
Abstract A solution of the partial differential equation describing transient thermal processes in the clad of a cylindrical fuel element is presented. This equation is solved by Laplace transform on the assumptions that the coolant temperature is not a function of time and the conduction in the longitudinal direction is neglected.
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Silicon Carbide Clad Graphite Matrix Fuel Elements

1960
A spherical graphite matrix element fueled with uranium dicarbide and clad with an impermeable layer of silicon carbide is described for use in pebble bed gas-cooled reactors. The following topics are discussed: fabrication techniques, cladding permeability tests, oxidation resistance, carbon density, crushing strength, impact resistance, fuel ...
KM Taylor, CH McMurtry
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The prediction problems of VVER fuel element cladding failure theory

Nuclear Engineering and Design, 2016
Abstract A method for forecasting of VVER fuel element (FE) cladding failure due to accumulation of deformation damage parameter, taking into account the fuel assembly (FA) loading history and the damage parameter distribution among FEs included in the FA, has been developed.
S.N. Pelykh, M.V. Maksimov, S.D. Ryabchikov   +2 more
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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 ...
V V Novikov, V I Kuznetsov
exaly   +2 more sources

Corrosion resistance of fuel element steel cladding in a lead coolant

Metal Science and Heat Treatment, 2007
The corrosion resistance of experimental and industrial steels considered as possible materials for fuel element cladding in the BREST reactor is investigated. Static corrosion tests in lead at 750°C lasting up to 1000 h, as well as metallographic and x-ray analysis, have been performed.
G. K. Zelenskii, A. G. Ioltukhovskii, M. V. Leont’eva-Smirnova, I. A. Naumenko, S. A. Tolkachenko   +4 more
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Thermal Stresses in Externally Clad Cylindrical Fuel Elements

Nuclear Science and Engineering, 1958
Equations for the thermal stresses developed in externally clad cylindrical fuel elements with radially symmetric temperature distribution are presented. The stresses developed in both a solid and a hollow fuel element under a given set of conditions are calculated and shown as an application of the equations. (auth)
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Cladding Material of Fuel Element of Fast Neutron Reactor

2017
Feasibility and benefits of applying grain boundary engineering (GBE) to the fuel cladding material 316 or 15-15Ti austenitic stainless steels of sodium-cooled fast reactor for reducing void swelling and creep are discussed. GBE can be used to greatly enhance the proportion of low Σ coincidence site lattice (CSL) grain boundaries that are mainly of ...
Fei Li, Lei Peng, Chuan Wang
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Cladding thickness of fuel elements by X-rays

2013
http://archive.org/details ...
Lowe, Beverly James., Sierer, Payson Dwight.   +1 more
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Detecting Cladding Leaks in Irradiated Fuel Elements by Neutron Radiography

1976
At Chalk River, performance limits for advanced fuels are established by irradiating multi-element assemblies until one or more elements develop a cladding leak. Post-irradiation identification of leaky elements is assisted by thermal neutron radiography, because marked changes in radiographic appearance occur due to the effects of light water coolant ...
exaly   +2 more sources

Finite element fracture mechanics analysis of creep rupture of fuel element cladding

Nuclear Engineering and Design, 1974
Abstract A finite element fracture mechanics technique is applied for simulating the elevated temperature creep rupture behavior of initially defected austenitic stainless steel fuel element cladding. The basic analytical approach consists of determining total instantaneous strain energy release rates G T , and the corresponding values of the ...
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