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Saturday, August 1, 2020 | History

2 edition of Characterization of emissions from plutonium-uranium oxide fuel fabrication found in the catalog.

Characterization of emissions from plutonium-uranium oxide fuel fabrication

E W. Bretthauer

Characterization of emissions from plutonium-uranium oxide fuel fabrication

by E W. Bretthauer

  • 3 Want to read
  • 4 Currently reading

Published by Environmental Protection Agency, Office of Research and Development, Environmental Monitoring and Support Laboratory, for sale by the National Technical Information Service in Las Vegas, Nev, Springfield, Va .
Written in English

    Subjects:
  • Nuclear fuels.,
  • Radioactive pollution.,
  • Plutonium.

  • Edition Notes

    StatementE.W. Bretthauer, A.J. Cummings, and S.C. Black.
    SeriesInteragency energy-environment research and development program report ; EPA-600/7-77-079
    ContributionsCummings, A J., Black, S C., Environmental Monitoring and Support Laboratory (Las Vegas, Nev.)
    The Physical Object
    Paginationix, 76 p. :
    Number of Pages76
    ID Numbers
    Open LibraryOL17536382M

    Downloadable (with restrictions)! The book summarizes the current state of the know-how in the field of perovskite materials: synthesis, characterization, properties, and applications. Most chapters include a review on the actual knowledge and cutting-edge research results. Thus, this book is an essential source of reference for scientists with research fields in energy, physics, . Plutonium(IV) oxide is the chemical compound with the formula PuO 2. This high melting-point solid is a principal compound of plutonium. It can vary in color from yellow to olive green, depending on the particle size, temperature and method of ance: Dark yellow crystals.

    MOX fuel, consisting of 7% plutonium mixed with depleted uranium, is equivalent to uranium oxide fuel enriched to about % 92U, assuming that the plutonium has about 60–65% 94Pu. If weapons-grade plutonium were used (>90% 94Pu), only about 5% plutonium would be needed in the mix. Finally, the book provides a comprehensive review for SOFC materials and fabrication techniques. A series of useful scientific appendices rounds off the book. Solid oxide fuel cell technology is a standard reference for all those researching this important field as well as those working in the power industry.

    Uranium Processing and Fuel Fabrication Nuclear power facilities use domestically produced fuel products, based on natural uranium. Uranium processing and fabricating facilities typically refine uranium ore concentrate (generally called “yellowcake”) into fuel bundles through several processing stages. A solid oxide fuel cell (or SOFC) is an electrochemical conversion device that produces electricity directly from oxidizing a fuel. Fuel cells are characterized by their electrolyte material; the SOFC has a solid oxide or ceramic electrolyte.


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Characterization of emissions from plutonium-uranium oxide fuel fabrication by E W. Bretthauer Download PDF EPUB FB2

CONCLUSION The following conclusions concerning the character of the plutonium- uranium stack emissions from a typical mixed Oxide fuel fabrication facility can be made from this research: 1.

Approximately nanocuries (nCi) of plutonium was emitted into the atmosphere per kilogram (Teg) of plutonium fabricated into mixed oxide fuel. Characterization of emissions from plutonium-uranium oxide fuel fabrication (OCoLC) Material Type: Government publication, National government publication: Document Type: Book: All Authors / Contributors: E W Bretthauer; A J Cummings; S C Black; Environmental Monitoring and Support Laboratory (Las Vegas, Nev.).

Recycling plutonium into mixed-oxide (MOX) fuel for nuclear reactors is being given serious consideration as a safe and environmentally sound method of managing plutonium from weapons programs. Planning for the proper design and safe operation of the MOX fuel fabrication.

Plutonium uranium mixed oxide (MOX) fuels are currently used in nuclear light water reactors. Thorium can be found in pristine as well as irradiated MOX samples. In normal conditions this element is only present in one oxidation state (IV), therefore its characterization can be used as a solid base for later studies of other actinides with the same oxidation by: 4.

Plutonium uranium mixed oxide (MOX) fuels are currently used in nuclear reactors. The actinides in these fuels need to be analyzed after irradiation for. SAFETY OF URANIUM AND PLUTONIUM MIXED OXIDE FUEL FABRICATION FACILITIES Specific Safety Guide IAEA Safety Standards Series No.

SSG-7 STI/PUB/ (84 pp. ) ISBN –92–0––0 Price: € THE MANAGEMENT SYSTEM FOR FACILITIES AND ACTIVITIES Safety Requirements IAEA Safety Standards Series No. GS-R-3 STI/PUB/. INTERNATIONAL ATOMIC ENERGY AGENCY, Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities, IAEA Safety Standards Series No.

SSG-7, IAEA, Vienna (). Download to: EdNote BibTeX *use BibTeX for Zotero. IAEA Safety Standards Series No. SF-1 () Safety through international standards IAEA Safety Standards Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities for protecting people and the environment No.

SSG-7 Specific Safety Guide IAEA Safety Standards Series No. SSG-7 1 High temperature solid oxide fuel cell (SOFC) technology is a promising power generation option that features high electrical efficiency and low emissions of environmentally polluting gases such as CO2, NOox and SOx.

It is ideal for distributed stationary power generation applications where both high-efficiency electricity and high-quality heat are in strong demand.

High temperature solid oxide fuel cell (SOFC) technology is a promising power generation option that features high electrical efficiency and low emissions of environmentally polluting gases such as CO2, NOox and SOx.

Sarikaya A., Buyukaksoy A., Dogan F. () Current Status of Fabrication of Solid Oxide Fuel Cells for Emission-Free Energy Conversion. In: Dincer I., Colpan C., Kadioglu F. (eds) Causes, Impacts and Solutions to Global : Ayhan Sarikaya, Aligul Buyukaksoy, Fatih Dogan.

In contrast, such oxide-ionic and hole conducting behavior was well suppressed at reduced temperatures below °C [, ], with the H 2 fluxes showing a water vapor independence in the cathodes and a beneficial increase with water vapor in the anodes for a Author: Yongcheng Tong, Yue Wang, Changsong Cui, Shiwei Wang, Bin Xie, Ranran Peng, Chusheng Chen, Zhonglian.

Request PDF | Fabrication and characterization of CeO 2 pellets for simulation of nuclear fuel | Cerium Oxide, CeO2, has been shown as a surrogate material to understand irradiated Mixed Oxide. Due to its many potential benefits, including high electrical efficiency and low environmental emissions, solid oxide fuel cell (SOFC) technology is the subject of extensive research and development efforts by national laboratories, universities, and private industries.

Finally, the book provides a comprehensive review for SOFC materials and fabrication techniques. A series of useful scientific appendices rounds off the book.

Solid oxide fuel cell technology is a standard reference for all those researching this important field as well as those working in the power by: Description.

This Safety Guide supplements the Safety Requirements publication Safety of Fuel Cycle Facilities and addresses all the stages in the life cycle of uranium fuel fabrication facilities, with emphasis being placed on design and operation.

8nm cerium oxide is surface functionalised for diesel compatibility and added to fuel at a level of ppm. Static engine tests and large scale field trials show that engine fuel consumption is reduced by % and emissions, particularly of black carbon particulates and unburnt hydrocarbons are reduced by >15%.

field of fast reactor fuel and fuel pin fabrication. He is presently Head of Fast Reactor Fuel Section, Radiometallurgy Division, BARC. Mr S. Majumdar, B.E., Metallurgy, is a graduate from 11th batch of BARC Training School.

His expertise is in the field of fabrication and characterization of nuclear fuels, both for thermal and fast Size: KB. On the anode (fuel electrode) side the gaseous fuel is oxidized according to equation (in the case of a hydrogen fuel): 2H 2(g) + 2O 2-→ 2H 2 O + 4e.

The electrons flow through the external electrical circuit. On the cathode (air electrode) side, oxygen reacts with incoming electrons and ions O 2-are formed: O 2(g) + 4e-→ 2O Cited by: A computer-controlled servo press forms the overcoated particles into the final fuel shape, with a series of heat treatments up to °C to carbonize and purify the graphite matrix.

Compact metrology, characterization and determinations of maximum defect populations are performed to NQA-1 standards prior to reactor insertion. Plutonium–uranium, with about 15–30 mol.% plutonium, can be used as a nuclear fuel for fast breeder reactors.

Its pyrophoric nature and high susceptibility to corrosion to the point of self-igniting or disintegrating after exposure to air require alloying with other ciation: /pluːˈtoʊniəm/ ​(ploo-TOH-nee-əm).Unclassified NEA/NSC/R()5 needed in fuel for fabrication and for understanding performance.

The WPMM’s objective is to promote the influences the thermal gradient in an oxide fuel pellet. This directly erns impacts conc such as centreline temperature, and thus the margins for fuel melting, and grain growth.

This work studied a way to reclaim uranium from contaminated UO2 oxide scraps as a sinterable UO2 powder for UO2 fuel pellet fabrication, which included a dissolution of the uranium oxide scraps in a carbonate solution with hydrogen peroxide and a UO4 precipitation step.

Dissolution characteristics of reduced and oxidized uranium oxides were evaluated in a Cited by: 4.