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An analysis of the in-reactor defect behaviour of u3si and u-si-al fuel elements

An analysis of the in-reactor defect behaviour of u3si and u-si-al fuel elements PDF Author: K. D. Cotnam
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


An analysis of the in-reactor defect behaviour of u3si and u-si-al fuel elements

An analysis of the in-reactor defect behaviour of u3si and u-si-al fuel elements PDF Author: K. D. Cotnam
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


In-reactor defect behaviour of u-si-al fuel elements

In-reactor defect behaviour of u-si-al fuel elements PDF Author: M. B. Watson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


The in-reactor defect behaviour of u-si-al fuel elements

The in-reactor defect behaviour of u-si-al fuel elements PDF Author: K. D. Cotnam
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


An analysis of the in-reactor defect behaviour on zirconium alloy clad u3si fuel elements

An analysis of the in-reactor defect behaviour on zirconium alloy clad u3si fuel elements PDF Author: M. A. Feraday
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


U Uranium

U Uranium PDF Author:
Publisher: Springer Science & Business Media
ISBN: 3662060140
Category : Science
Languages : en
Pages : 371

Book Description
The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.

Out-reactor defect behaviour of u3si elements containing a corrodible layer and u3si end plugs

Out-reactor defect behaviour of u3si elements containing a corrodible layer and u3si end plugs PDF Author: J. L. Conversi
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


Performance of Low-enriched U3Si2-aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor

Performance of Low-enriched U3Si2-aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Six high-density, low-enriched U3Si2-Al dispersion fuel elements have been tested in the Oak Ridge Research Reactor (ORR). The elements were geometrically identical to standard ORR elements. The uranium density in the fuel meat ranged between 4.6 and 5.2 Mg/m3. The elements were fabricated by B and W, CERCA, and NUKEM using their normal materials and fabrication practices, with minor modifications necessitated by the new fuel. The U3Si2 contained minor amounts of USi, U3Si and/or uranium solid solution. The elements were irradiated to approximately normal ORR burnup, and three elements were irradiated twice as long, to average burnups of approx. 80% of the initially contained 235U, well above the burnups normally achieved in research and test reactors. Peak burnups of 98% were achieved. Following suitable cooling periods, the elements were subjected to a series of nondestructive and destructive examinations. The behavior of the fuel was found to be entirely consistent with the known irradiation behavior of the constituent phases. The extremely stable swelling behavior of the U3Si2 phase dominated in all cases. The plates showed small, uniform thickness changes. Blister threshold temperatures were greater than or equal to550°C. It is concluded that low-enriched U3Si2-Al dispersion fuel elements will perform at least as well in research and test reactors with power densities up to that of the ORR as the highly enriched UAl(subscript x)-Al and U3O-Al dispersion fuels currently being used. There were no indications that use of this fuel under substantially more stringent conditions might be precluded. 10 refs., 87 figs., 9 tabs.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 900

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.

A proposal to examine the defect behaviour of a u-si-a1 fuel element containing a disc-type detection device with a corrodible strip

A proposal to examine the defect behaviour of a u-si-a1 fuel element containing a disc-type detection device with a corrodible strip PDF Author: M. B. Watson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description


A proposal to examine the defect behaviour of a fuel element containing a graphite disc impregnated with uo2 between u-si-a1 rods (phase 2).

A proposal to examine the defect behaviour of a fuel element containing a graphite disc impregnated with uo2 between u-si-a1 rods (phase 2). PDF Author: M. B. Watson
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

Book Description