A Combined Fission Gas Release and Swelling Model for Fuel During Irradiation PDF Download
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Author: J.W. Harrison
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
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Book Description
Author: J.W. Harrison
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
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Author: Nathan Christopher Andrews
Publisher:
ISBN:
Category :
Languages : en
Pages : 149
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Book Description
Fuel swelling and fission gas generation for fast reactor fuels are of high importance since they are among the main limiting factors in the development of metallic fast reactor fuel. Five new fission gas and swelling modules for the fast reactor metallic fuel code FEAST-METAL were developed. This increases the number of degrees of freedom in the code and enhances the science -based modeling options for fuel swelling. All of the modules developed were benchmarked against data from EBRII. Particularly, the code was benchmarked against U-19Pu-lOZr fuel and was applied to U-6Zr fuel. The modifications made still kept the overall GRSIS algorithm present in the code. The GRSIS model tracks "closed" and "open" bubbles. The new modifications increased the number of closed bubble groups used in the algorithm, inserted a model that changed the bubble groups from being based on constant volumes to ones with constant numbers of atoms, added phase dependence and reexamined closed bubble spacing through the implementation of a Monte-Carlo algorithm to calculate the effective distance between the nearest bubbles. All model options added to the code predicted the swelling, fission gas release and cladding strain effectively for the benchmark cases. However, significant differences in the results were fotind when the codes were applied to long-term U-6Zr fuel. The differences in the results cannot be resolved without more data on fuel behavior under irradiation; particularly, breeder fuel (blanket) data is needed to develop effective benchmarks. Until more data becomes available, it is advisable to use the original two group constant volume version of the code and the phase dependent version of the code and compare the results. The latter offers a much more scientifically based version of the code. Sensitivity analysis to the number of bubble groups indicate limited benefit may be obtained by using more than 2 bubble sizes. Additionally, care should be taken to ensure that the axial nodding of the fuel be such that the axial mesh length is smaller than 10% of the fuel length. Furthermore, if the FEAST code is to be used in a coupled fashion with the coolant sub-channel analysis code COBRA, the accuracy of the results depend on the model used for fuel swelling.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 15
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Book Description
A program is in progress at Battelle-Columbus which is aimed at developing a basic understanding of the mechanisms and processes which contribute to the phenomenology of swelling and fission gas release in nuclear fuel materials during irradiation. As part of this program, neutron radiography has been used to obtain data on the dimensional changes of fuel specimens periodically during irradiation. This data is used to develop plots of fuel swelling as a function of burnup for the specimens under irradiation. These data show a decided nonlinearity of swelling with accumulated burnup for many specimens, and it has been postulated that the shape of the curves is due, at least in part, to the gas release characteristics of the specimens. Accordingly, it was considered advantageous to develop a system to continuously monitor fission gas release from the fuel during irradiation. The system developed consists of a null-balance pressure transducer attached directly to a clad fuel specimen in the capsule. Fission gases escaping from the fuel collect within the cladding and exert pressure on a diaphragm in the transducer. A balancing pressure is introduced on the other side of the diaphragm and the null-balance position of the diaphragm is detected by an electrical contact which is part of a detection circuit. Instrumentation is provided to monitor the balance pressure, and the fission gas temperature and pressure is correlated with the known fission gas generation rate to calculate the fractional release from the fuel. In addition to monitoring fission gas release, the system also provides information on cladding integrity. Cladding failure is detected as a large reduction in pressure while operating at essentially constant temperature. This system has been used successfully in two irradiation experiments at fuel and cladding temperatures in excess of 1700 C. The data it provides on fission gas release has been used in conjunction with swelling data from neutron radiography to provide considerable insight into the phenomenology of the behavior of nuclear fuels during irradiation.
Author: Gordon G. Bentle
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 76
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Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
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Book Description
Author:
Publisher: Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN:
Category : Science
Languages : en
Pages : 572
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Book Description
Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Author: Ralph O. Meyer
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 68
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Book Description
Author: M. J. F. Notley
Publisher:
ISBN:
Category : Fission products
Languages : en
Pages : 39
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Author: M. H. Wood
Publisher:
ISBN:
Category :
Languages : en
Pages : 34
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 12
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Book Description
This document discusses a new version of the dispersion fuel behavior model currently being incorporated in DART, which has been generated. The model's description of fuel swelling - more specifically, the evaluation of fission-gas bubble morphology - is significantly improved. Although some of the assumptions underlying the basic model are derived from systems other than U3Si2, it represents a physically realistic interpretation of the observed irradiation behavior of U3Si2 over a wide range of fission densities and fission rates.
