Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements Metadata

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Title

  • Main Title Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements

Creator

  • Author: Wilson, W. B.
    Creator Type: Personal
  • Author: LaBauve, R. J.
    Creator Type: Personal
  • Author: England, T. R.
    Creator Type: Personal

Publisher

  • Name: Los Alamos National Laboratory
    Place of Publication: New Mexico

Date

  • Creation: 1982-01-01

Language

  • English

Description

  • Content Description: Comparisons with integral measurements have demonstrated the accuracy of CINDER codes and libraries in calculating aggregate fission-product properties, including neutron absorption, decay power, and decay spectra. CINDER calculations have, alternatively, been used to supplement measured integral data describing fission-product decay power and decay spectra. Because of the incorporation of the extensive actinide library and the use of ENDF/B-V data, it is desirable to compare the inventory of individual nuclides obtained from tandem EPRI-CELL/CINDER-2 calculations with those determined in documented benchmark inventory measurements of spent reactor fuel. The development of the popular /sup 148/Nd burnup measurement procedure is outlined, and areas of uncertainty in it and lack of clarity in its interpretation are indicated. Six inventory samples of varying quality and completeness are examined. The power histories used in the calculations have been listed for other users.
  • Physical Description: 28 pages

Subject

  • Keyword: Bwr Type Reactors
  • Keyword: Radioactive Materials
  • Keyword: Computer Calculations
  • Keyword: Reactor Components
  • Keyword: Comparative Evaluations
  • Keyword: Spent Fuel Elements
  • Keyword: After-Heat
  • Keyword: Isotopes
  • Keyword: Intermediate Mass Nuclei
  • Keyword: Water Cooled Reactors
  • Keyword: Fission Products
  • Keyword: Water Moderated Reactors 210100* -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled
  • Keyword: Materials
  • Keyword: Even-Even Nuclei
  • Keyword: Nuclei
  • Keyword: Reactors
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Burnup
  • Keyword: Fuel Elements
  • STI Subject Categories: 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
  • Keyword: Pwr Type Reactors
  • Keyword: Activity Levels
  • Keyword: Rare Earth Nuclei
  • Keyword: Neodymium Isotopes
  • Keyword: Neodymium 148
  • Keyword: Stable Isotopes

Source

  • Conference: Thermal reactor benchmark calculations, techniques, results and applications seminar, Upton, NY, USA, 17 May 1982

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE82021772
  • Report No.: LA-UR-82-2341
  • Report No.: CONF-820566-7
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5043554
  • Archival Resource Key: ark:/67531/metadc1056589

Note

  • Display Note: NTIS, PC A03/MF A01.
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