Results 141 to 150 of about 821 (181)

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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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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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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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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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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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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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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Development and verification of a failure-analysis model for FBR fuel-element cladding

Nuclear Engineering and Design, 1985
Abstract Failure-analysis models for Fast-Breeder-Reactor (FBR) fuel elements cladded with 20% cold-worked Type 316 stainless steel are reviewed. A model based on linear damage accumulation and time-to-failure correlations is developed and tested against the data base for pressurized tubes. The model goes beyond the state of the art for damage models
S.L. Wu, M.C. Billone
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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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Stochastic thermal stress analysis of clad cylindrical fuel elements

Nuclear Engineering and Design, 1975
After a review of deterministic elastic thermal stress analysis by means of the displacement method for a cylindrical system in which the temperature distribution is not only radially variable but azimuthally and axially variable also, a method is shown for the determination of the statistical moments of the stress components when (a) the outer ...
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