Examination of Irradiated Experimental NRU Fuel Rods PDF Download
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Author: S. H. Paine Publisher: ISBN: Category : Expansion (Heat) Languages : en Pages : 56
Book Description
A clad rod having square cross section was found to have failed by typical internal aqueous attack of the core material. Cause of initial perforation cannot be assigned with certainty.
Author: S. H. Paine Publisher: ISBN: Category : Expansion (Heat) Languages : en Pages : 56
Book Description
A clad rod having square cross section was found to have failed by typical internal aqueous attack of the core material. Cause of initial perforation cannot be assigned with certainty.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Examination of flat, natural uranium plates mechnnically clad with aluminum sheaths revealed a tendency for thermal contact between clad and core to diminish as a result of elongation and roughening of the uranium. The assemblies containing beta-quenched uranium showed less damage than those in which material rolled in the high alpha range was used. A clad rod having square cross section was found to have failed by typical internal aqueous attack of the core material. Cause of initial perforation cannot be assigned with certainty. (auth).
Author: D. F. Sears Publisher: ISBN: Category : Languages : en Pages : 0
Book Description
Aecl has submitted an environmental impact statement (eis) to evaluate the concept of nuclear fuel disposal at depth in crystalline rock of the canadian shield. in this disposal concept used fuel would be emplaced in corrosion-resistant containers which would be surrounded by clay-based buffer and backfill materials. once groundwater is able to penetrate the buffer and corrosion-resistant container, radionuclides could be transported from the waste form to the surrounding geosphere, and eventually to the biosphere. the release of radionuclides from the waste form and their subsequent transport would be determined by the geochemistry of the disposal vault and surrounding geosphere. organic substances affect the geochemistry of radionuclides through complexation reactions that increase solubility and alter mobility, be affecting the redox of certain radionuclides and be providing food for microbes. the purpose of this study was to determine whether the buffer and backfill materials proposed for use in a disposal vault contain organics that could be leached by groundwarer in large enough quantities to complex with radionuclides and affect their mobility within the disposal vault and surrounding geosphere. buffer material, made from a mixture of 50 wt.% avonlea sodium bentonite and 50 wt.% silica sand, was extracted with deionized water to determine the release of dissolved organic carbon, humic acid and fulvic acid. the effect of radiation and heat from the used fuel was simulated by treating samples of buffer before leaching to various amounts of heat (60 degrees c and 90 degrees c) for periods of 2,4 and 6 weeks, and to ionizing radiation with doses of 25 kgy and 50 kgy. humic substances were isolated from the leachates to determine the concentrations of humic and fulvic acids and to determine their functional group content by acid-base titrations. the results showed that groundwater could leach significant amounts of organics that would complex with radionuclides such as the actinides, affecting their solubility and transport within the disposal vault and possible the surrounding geosphere. heating and radiation affect the amount and nature of leachable organics. however, one of the key parameters that needs to be addressed is the mobility of organic molecules through an intact buffer and backfill.
Author: J. P. Adams Publisher: ISBN: Category : Languages : en Pages : 0
Book Description
This report summarizes the characterization studies performed on 100 uranium fuel rods irradiated in the br-3 reactor under the direction of belgonucleaire, s.a. in mol, belgium. the irradiation history and fuel content, as reported by belgonucleaire, are included for all fuel rods as are the results of nondestructive and destructive examinations performed by eg&g idaho, inc., and argonne-west personnel on a selected sample of the fuel rods. these fuel rods are scheduled for use in experiments at the power burst facility (in the severe fuel damage experiment series) and in the transient reactor test facility (treat) (in the source term experiment program) at the idaho national engineering laboratory.
Author: S. H. Paine Publisher: ISBN: Category : Irradiation Languages : en Pages : 48
Book Description
A Los Alamos Scientific Laboratory fuel-bearing assembly was irradiated in the Materials Testing Reactor and subsequently examined at ANL. The design was found to be adequate for containing specimens irradiated to high burnup levels if certain defects introduced by the fabrication procedure are corrected.
Author: Atomic Energy of Canada Limited Publisher: McGill-Queen's Press - MQUP ISBN: 9780773516014 Category : Business & Economics Languages : en Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
Author: International Atomic Energy Agency Publisher: International Atomic Energy Agency ISBN: 9789201627094 Category : Technology & Engineering Languages : en Pages :
Book Description
This publication represents a summary and proceedings of two technical meetings on the subjects of 1) hot cell post-irradiation examination (PIE) techniques and poolside inspection of water reactor fuel assemblies, and 2) fuel rod instrumentation and in-pile measurement techniques. It provides an overview of the status of in-pile and post-irradiation techniques of water reactor fuel examination with an emphasis on experimental methods applied to high burnup fuel. Further important items addressed at these meetings were the information on progress achieved in non-destructive and destructive PIE techniques used for investigation of water reactor fuels, advanced PIE techniques such as 3-D tomography, as well as advanced in-pile measurement techniques for a better understanding of mechanisms of fuel behavior under irradiation.
Author: S. H. Paine
Author: S. H. Paine
Author: 
Author: J. Williams
Author: W. R. Green
Author: D. F. Sears
Author: J. P. Adams
Author: S. H. Paine
Author: D. F. Sears
Author: Atomic Energy of Canada Limited
Author: International Atomic Energy Agency