Design and Operation of Gamma Scan and Fission Gas Sampling Systems for Characterization of Irradiated Commercial Nuclear Fuel PDF Download
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Author: C. A. Knox
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Category :
Languages : en
Pages :
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Author: C. A. Knox
Publisher:
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Category :
Languages : en
Pages :
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Author:
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Category : Power resources
Languages : en
Pages : 508
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Author:
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Category :
Languages : en
Pages :
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The U.S. Global Nuclear Energy Partnership / Advanced Fuel Cycle Initiative (GNEP/AFCI) is developing metallic transmutation alloys as a fuel form to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. The AFCI program has irradiated and examined eleven metallic alloy transmutation fuel specimens to evaluate the feasibility of actinide transmutation in advanced sodium-cooled fast reactors and thermal reactor implementation. Initial results of postirradiation examinations indicated the irradiation performance of the actinide-bearing compositions is similar to uranium-plutonium-zirconium ternary metallic alloy fuels (U-xPu-10Zr). Further studies to characterize radial burnup profile, constituent migration, and fuel cladding chemical interaction (FCCI) are in progress. A microgamma scan system is being developed to analyze the radial distribution of fission products, such as Cs-137, Cs-134, Ru-106, and Zr-95, in irradiated fuel cross-sections. The microgamma scan system consists of a set of indexed sample collimator blocks and a sample holder, which interfaces with the INL Analytical Laboratory Hot Cell (ALHC) Gamma Scan System high purity germanium detector, multichannel analyzer, and removable collimators. The microgamma scan results will be used to evaluate radial burnup profile, cesium migration to the sodium bond and constituent migration within the fuel. These data will further clarify the comparative irradiation performance of actinide-bearing metallic transmutation fuel forms and uranium-plutonium-zirconium alloys. Preliminary measurements of the microgamma scan system will be discussed. A simplified model of the microgamma scan system was developed in MCNP and used to investigate the system performance and to interpret data from the scoping studies. Recommendations for improving the MCGS analyses are discussed.
Author: J. R. Phillips
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Category : Gamma ray spectrometry
Languages : en
Pages : 226
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Author:
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ISBN: 9789155490997
Category :
Languages : en
Pages : 94
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Author:
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Category : Aeronautics
Languages : en
Pages : 218
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Author:
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Category : Nuclear energy
Languages : en
Pages : 934
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Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188
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Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.
Author: United States. Energy Research and Development Administration
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Category : Energy conservation
Languages : en
Pages : 1324
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Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
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Category : Force and energy
Languages : en
Pages : 1680
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