Nuclear data to support computer code validation Metadata

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Title

  • Main Title Nuclear data to support computer code validation

Creator

  • Author: Fisher, S.E.
    Creator Type: Personal
  • Author: Broadhead, B.L.
    Creator Type: Personal
  • Author: DeHart, M.D.
    Creator Type: Personal
  • Author: Primm, R.T. III
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States)

Publisher

  • Name: Oak Ridge National Laboratory
    Place of Publication: Tennessee
    Additional Info: Oak Ridge National Lab., TN (United States)

Date

  • Creation: 1997-04-01

Language

  • English

Description

  • Content Description: The rate of plutonium disposition will be a key parameter in determining the degree of success of the Fissile Materials Disposition Program. Estimates of the disposition rate are dependent on neutronics calculations. To ensure that these calculations are accurate, the codes and data should be validated against applicable experimental measurements. Further, before mixed-oxide (MOX) fuel can be fabricated and loaded into a reactor, the fuel vendors, fabricators, fuel transporters, reactor owners and operators, regulatory authorities, and the Department of Energy (DOE) must accept the validity of design calculations. This report presents sources of neutronics measurements that have potential application for validating reactor physics (predicting the power distribution in the reactor core), predicting the spent fuel isotopic content, predicting the decay heat generation rate, certifying criticality safety of fuel cycle facilities, and ensuring adequate radiation protection at the fuel cycle facilities and the reactor. The U.S. in-reactor experience with MOX fuel is first presented, followed by information related to other aspects of the MOX fuel performance information that is valuable to this program, but the data base remains largely proprietary. Thus, this information is not reported here. It is expected that the selected consortium will make the necessary arrangements to procure or have access to the requisite information.
  • Physical Description: 18 p.

Subject

  • Keyword: Pwr Type Reactors
  • Keyword: Bwr Type Reactors
  • Keyword: Computer Codes
  • STI Subject Categories: 99 Mathematics, Computers, Information Science, Management, Law, Miscellaneous
  • Keyword: Mixed Oxide Fuels
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Computer Calculations
  • Keyword: Nuclear Data Collections
  • Keyword: Reactor Physics
  • STI Subject Categories: 22 Nuclear Reactor Technology
  • Keyword: Mixed Oxide Fuel Fabrication Plants
  • Keyword: Validation
  • Keyword: Plutonium

Source

  • Other Information: PBD: Apr 1997

Collection

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

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Other: DE98052495
  • Report No.: ORNL/TM--13422
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/582259
  • Office of Scientific & Technical Information Report Number: 582259
  • Archival Resource Key: ark:/67531/metadc693526

Note

  • Display Note: INIS; OSTI as DE98052495