Post-irradiation Evaluation of a Plate-type UO2 Fuel Element PDF Download
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Author: H. B. Meieran
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 86
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Book Description
Author: H. B. Meieran
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 86
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Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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The premature failure of fuel Element M22, which had six compartments of 0.100-in.-thick, 96% TD UO/sub 2/ + 6 wt% ZrO/sub 2/ fuel, was attributed to the large irradiation-induced solid volume swelling of the UO/sub 2/ fuels. This volume swelling was the result of incomplete homogenization during fabrication of the mixed and sintered U/sup E/O/sub 2/ and U/sup N/O/sub 2/ fuel s in Element M22. In addition, heavy hydriding of the Ni-free Zircaloy-2 cladding occurred in the relatively hot areas adjacent to the fuel and to a lesser extent at the external cladding surfaces. By postulation, H/sub 2/ was apparently formed by the radiolytic decomposition of water entrapped between fuel and cladding after formation of the initial cladding defect, and was absorbed by the cladding so rapidly that it could not diffuse adequately down the thermal gradient to the cold side of the cladding. The corrosion behavior of the cladding was as expected and did not contribute to the hydriding. Analysis of the CR-X-3 loop operating history indicates that no abnormal conditions external to Element M22 existed in the loop other than U from inpile intentionally defected fuel elements. (auth).
Author: Roger Conant Waugh
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 146
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Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149
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Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.
Author: J. L. Bates
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 46
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Author:
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Category :
Languages : en
Pages :
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This article analyzes dimensional changes due to irradiation of monolithic plate-type nuclear fuel and compares results with finite element analysis of the plates during fabrication and irradiation. Monolithic fuel plates tested in the Advanced Test Reactor (ATR) at Idaho National Lab (INL) are being used to benchmark proposed fuel performance for several high power research reactors. Post-irradiation metallographic images of plates sectioned at the midpoint were analyzed to determine dimensional changes of the fuel and the cladding response. A constitutive model of the fabrication process and irradiation behavior of the tested plates was developed using the general purpose commercial finite element analysis package, Abaqus. Using calculated burn-up profiles of irradiated plates to model the power distribution and including irradiation behaviors such as swelling and irradiation enhanced creep, model simulations allow analysis of plate parameters that are either impossible or infeasible in an experimental setting. The development and progression of fabrication induced stress concentrations at the plate edges was of primary interest, as these locations have a unique stress profile during irradiation. Additionally, comparison between 2D and 3D models was performed to optimize analysis methodology. In particular, the ability of 2D and 3D models account for out of plane stresses which result in 3-dimensional creep behavior that is a product of these components. Results show that assumptions made in 2D models for the out-of-plane stresses and strains cannot capture the 3-dimensional physics accurately and thus 2D approximations are not computationally accurate. Stress-strain fields are dependent on plate geometry and irradiation conditions, thus, if stress based criteria is used to predict plate behavior (as opposed to material impurities, fine micro-structural defects, or sharp power gradients), unique 3D finite element formulation for each plate is required.
Author: R. C. Daniel
Publisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 294
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Author: John D. Eichenberg
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 28
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Author: T. J. Slosek
Publisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 78
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Author: J. M. Gerhart
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 124
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