Swelling of uranium silicide fuel during post-irradiation heating

Swelling of uranium silicide fuel during post-irradiation heating PDF Author: R. B. Matthews
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Swelling of uranium silicide fuel during post-irradiation heating

Swelling of uranium silicide fuel during post-irradiation heating PDF Author: R. B. Matthews
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Mechanistic Interpretation of an Observed Rate Dependence of Low Temperature Swelling of Irradiated Uranium Silicide Dispersion Fuels

Mechanistic Interpretation of an Observed Rate Dependence of Low Temperature Swelling of Irradiated Uranium Silicide Dispersion Fuels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 21

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Recent experimental observations on low temperature swelling of irradiated uranium silicide dispersion fuels have indicated that the growth of fission gas bubbles appears to be affected by fission rate. The swelling curve of the material exhibits a distinct knee'' that shifts to higher fission density with increased fission rate due to higher enrichments. Current state-of-the-art models for fission gas behavior do not predict such a dependence. Indirect evidence from various experiments leads the present authors to speculate that a dense network of subgrain boundaries forms at a dose corresponding to the knee'' in the swelling curve, upon which gas bubbles nucleate and then grow at an accelerated rate compared to those in the bulk material. A theoretical formulation is presented wherein the stored energy in the material is concentrated on a network of crystallization'' sites which diminish with dose due to interaction with radiation produced defects (vacancy-impurity pairs). Recrystallization is induced by statistical fluctuations when the energy per site is high enough such that the creation of grain boundary surfaces is offset by the creation of strain free volumes with a resultant net decrease in the free energy of the material. This formulation is shown to provide a reasonable interpretation of the observed phenomena. 11 refs., 7 figs.

Irradiation Effects in Nuclear Fuels

Irradiation Effects in Nuclear Fuels PDF Author: J. A. L. Robertson
Publisher: New York : Gordon and Breach
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 328

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Detailed Analysis of Uranium Silicide Dispersion Fuel Swelling

Detailed Analysis of Uranium Silicide Dispersion Fuel Swelling PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 21

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Book Description
Swelling of U3Si and U3Si2 is analyzed. The growth of fission gas bubbles appears to be affected by fission rate, fuel loading, and microstructural change taking place in the fuel compounds during irradiation. Several mechanisms are explored to explain the observations. The present work is aimed at a better understanding of the basic swelling phenomenon in order to accurately model irradiation behavior of uranium silicide disperson fuel. 5 refs., 10 figs.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 632

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Book Description
NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Irradiation Mixing of Al Into U3Si

Irradiation Mixing of Al Into U3Si PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 6

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Thermal and irradiation induced intermixing of uranium silicide reactor fuels with the aluminum cladding is an important consideration in understanding their fission gas and fuel swelling behavior. The authors have used Rutherford backscattering to follow the behavior of an Al thin film on U3Si and U3Si2 during 1.5 MeV Kr ion irradiation at temperatures of 30 and 350 C. After an initial dose during which no intermixing occurs, the Al mixes quickly into U3Si. The threshold dose is believed to be associated with an oxide layer between the Al and the uranium silicide. At 300 C and doses greater than threshold, rates of mixing and aluminide phase growth are extracted.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1162

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1338

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A New Swelling Model and Its Application to Uranium Silicide Research Reactor Fuel

A New Swelling Model and Its Application to Uranium Silicide Research Reactor Fuel PDF 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.

Some Recent Observations on the Radiation Behavior of Uranium Silicide Dispersion Fuel

Some Recent Observations on the Radiation Behavior of Uranium Silicide Dispersion Fuel PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 20

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Addition of B4C burnable poison results in higher plate swelling in both U3Si2 and U3Si-Al dispersion fuel plates and also decreases the blister threshold temperature of these plates. Prolonged annealing of U3Si2-Al fuel plates produced no blister after 696 hours at 400°C. Blister formation started between 257 hours and 327 hours at 425°C and between 115 hours and 210 hours at 450°C. Operation with breached cladding resulted in pillowing of an U3Si-Al fuel plate due to reaction of the fuel core with coolant water. 4 refs., 10 figs., 2 tabs.