THO2-based pellet fuels, their properties, methods of fabrication, and irradiation performance
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THO2-based pellet fuels, their properties, methods of fabrication, and irradiation performance a critical assessment of the state of thetechnology and recommendations for further work by Pacific Northwest Laboratory.

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Published by Dept. of Energy, Pacific Northwest Laboratory, for sale by the National Technical Information Service] in Richland, Wash, [Springfield, Va .
Written in English

Subjects:

  • Thorium.,
  • Nuclear fuels.

Book details:

Edition Notes

Statementby P. E. Hart ... [et al.] ; prepared for the U.S. Department of Energy ... .
SeriesPNL ; 3064, PNL (Series) -- 3064.
ContributionsHart, P. E., 1940-, United States. Dept. of Energy.
The Physical Object
Pagination168 p. in various pagings :
Number of Pages168
ID Numbers
Open LibraryOL15243588M

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This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. Request PDF | Fabrication Technologies for ThO2-based Fuel | Fuel fabrication technology, particularly once through utilization of uranium, has been . ThO2-based pellet fuels - their properties, methods of fabrication, and irradiation performance: a critical assessment of the state of the technology and recommendations for further work Article P.   The study of thorium dioxide/thoria ThO 2-based fuel irradiation behavior is significantly less advanced than that of uranium dioxide (UO 2) fuel, although ThO 2 possesses superior thermal conductivity, thermal expansion, higher melting temperature, and oxidation resistance that may improve both fuel performance and : J. S. Bell, P. K. Chan, A. Prudil.

Ceramics are widely accepted as nuclear reactor fuel materials, for both metal clad ceramic and all-ceramic fuel designs. Metal clad UO 2 is used commercially in large tonnages in five different power reactor by: 6. Another incentive to use thorium in once-through fuel cycle is the possibility of incineration of weapons-grade plutonium (WPu) in combination with thorium in light-water reactors of WWER type to burn and not breed Pu. For this, mixed thorium plutonium oxide, containing ~5% PuO2, could be used as driver Size: 1MB. The pellet land width and the dish radius influence the occurrence of maximum temperature on the land, which dictates the axial gap requirement within the fuel element. From the pellet fabrication point of view, the slight increase in land width was found essential for . Thorium based Fuel can be used in all current reactor types, including PWRs, WWERs, BWRs, HWRs, FBRs, HTRs/HTGRs. The thorium fuel systems contains a high fissile fuel zone (seed region) and the fertile thorium part of the fuel (the blanket).Author: Sadegh Beigi, Amir Charkhi, Mohammad Amin Sobati.

  Recycled uranium and MOX fuel technologies Options for Plutonium Management: MOX, ThO2-based fuels and inert matrices Hj. Matzke, J. Van Geel, and J. Magill European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach , D Karlsruhe, Federal Republic of Germany © British . In this paper, a two-dimensional characteristic unit was used to simulate the thermal–mechanical performance of a fully ceramic microencapsulated (FCM) fuel pellet, and the criterion of FCM structure integrity was discussed. FCM structure integrity can be reflected though the integrity of the silicon carbide (SiC) matrix or SiC layers because of the excellent fission retention Author: Ping Chen, Suizheng Qiu, Shichao Liu, Yi Zhou, Yong Xin, Shixin Gao, Xi Qiu, Huaiyu Lu. MOX and (Th-LEU) MOX type fuels in the area of fabrication, performance modelling, out-of –pile properties evaluation, in-pile irradiation and PIE 3. Studies for open fuel cycle such as spent fuel behaviour during extended storage, characterization of spent fuel for waste management 2. Physicochemical properties and cell viability were studied pre- and post-sterilization. The efficiency of irradiation sterilization was performed by a test of sterility using 1 × CFU/mL of Escherichia coli, Staphylococcus aureus, and Candida albicans. Microbiological monitoring revealed that both methods were sufficient for sterilization.