Explore: Fission Gases

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Source: The Open Library

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1FASTGRASS, a mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions

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“FASTGRASS, a mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions” Metadata:

  • Title: ➤  FASTGRASS, a mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions
  • Author:
  • Language: English
  • Number of Pages: Median: 157
  • Publisher: ➤  Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission - Supt. of Docs., U.S. G.P.O. [distributor]
  • Publish Date:
  • Publish Location: Washington, DC

“FASTGRASS, a mechanistic model for the prediction of Xe, I, Cs, Te, Ba, and Sr release from nuclear fuel under normal and severe-accident conditions” Subjects and Themes:

Edition Identifiers:

Access and General Info:

  • First Year Published: 1992
  • Is Full Text Available: No
  • Is The Book Public: No
  • Access Status: No_ebook

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    2Convective-diffusive transport of fission products in the gap of a failed fuel element

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    “Convective-diffusive transport of fission products in the gap of a failed fuel element” Metadata:

    • Title: ➤  Convective-diffusive transport of fission products in the gap of a failed fuel element
    • Author:
    • Language: English
    • Number of Pages: Median: 10
    • Publisher: ➤  Chalk River Laboratories - Chalk River Laboratories, Fuel Engineering Branch
    • Publish Date:
    • Publish Location: Chalk River, Ont

    “Convective-diffusive transport of fission products in the gap of a failed fuel element” Subjects and Themes:

    Edition Identifiers:

    Access and General Info:

    • First Year Published: 1995
    • Is Full Text Available: No
    • Is The Book Public: No
    • Access Status: No_ebook

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    3Post-irradiation thermal release study of fission gases from fuel pellets

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    “Post-irradiation thermal release study of fission gases from fuel pellets” Metadata:

    • Title: ➤  Post-irradiation thermal release study of fission gases from fuel pellets
    • Author:
    • Language: English
    • Number of Pages: Median: 13
    • Publisher: Bhabha Atomic Research Centre
    • Publish Date:
    • Publish Location: Bombay

    “Post-irradiation thermal release study of fission gases from fuel pellets” Subjects and Themes:

    Edition Identifiers:

    Access and General Info:

    • First Year Published: 1971
    • Is Full Text Available: No
    • Is The Book Public: No
    • Access Status: No_ebook

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    4Measurement of fission gas release from irradiated nuclear fuel elements

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    “Measurement of fission gas release from irradiated nuclear fuel elements” Metadata:

    • Title: ➤  Measurement of fission gas release from irradiated nuclear fuel elements
    • Author:
    • Language: English
    • Number of Pages: Median: 12
    • Publisher: Bhabha Atomic Research Centre
    • Publish Date:
    • Publish Location: Mumbai

    “Measurement of fission gas release from irradiated nuclear fuel elements” Subjects and Themes:

    Edition Identifiers:

    Access and General Info:

    • First Year Published: 2005
    • Is Full Text Available: No
    • Is The Book Public: No
    • Access Status: No_ebook

    Online Access

    Downloads Are Not Available:

    The book is not public therefore the download links will not allow the download of the entire book, however, borrowing the book online is available.

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      5Fission gas behaviour in safety experiments

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      “Fission gas behaviour in safety experiments” Metadata:

      • Title: ➤  Fission gas behaviour in safety experiments
      • Author:
      • Language: English
      • Publisher: Harwood Academic Publishers
      • Publish Date:
      • Publish Location: New York, N.Y - Switzerland

      “Fission gas behaviour in safety experiments” Subjects and Themes:

      Edition Identifiers:

      Access and General Info:

      • First Year Published: 1984
      • Is Full Text Available: No
      • Is The Book Public: No
      • Access Status: No_ebook

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      6The evolution of fission gas from overheated UO2

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      “The evolution of fission gas from overheated UO2” Metadata:

      • Title: ➤  The evolution of fission gas from overheated UO2
      • Author:
      • Language: English
      • Number of Pages: Median: 14
      • Publisher: UKAEA
      • Publish Date:
      • Publish Location: Culceth

      “The evolution of fission gas from overheated UO2” Subjects and Themes:

      Edition Identifiers:

      Access and General Info:

      • First Year Published: 1986
      • Is Full Text Available: No
      • Is The Book Public: No
      • Access Status: No_ebook

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      7Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation

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      “Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation” Metadata:

      • Title: ➤  Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation
      • Author:
      • Language: English
      • Number of Pages: Median: 189
      • Publisher: DUP Science
      • Publish Date:
      • Publish Location: Delft, The Netherlands

      “Helium and fission gas behaviour in magnesium aluminate spinel and zirconia for actinide transmutation” Subjects and Themes:

      Edition Identifiers:

      Access and General Info:

      • First Year Published: 2003
      • Is Full Text Available: No
      • Is The Book Public: No
      • Access Status: No_ebook

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      8Fission gas behaviour in water reactor fuels

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      Book's cover

      “Fission gas behaviour in water reactor fuels” Metadata:

      • Title: ➤  Fission gas behaviour in water reactor fuels
      • Author:
      • Language: English
      • Number of Pages: Median: 559
      • Publisher: ➤  Nuclear Energy Agency, Organisation for Economic Co-operation and Development
      • Publish Date:
      • Publish Location: Paris, France

      “Fission gas behaviour in water reactor fuels” Subjects and Themes:

      Edition Identifiers:

      Access and General Info:

      • First Year Published: 2002
      • Is Full Text Available: No
      • Is The Book Public: No
      • Access Status: No_ebook

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