Nuclear data needs for application in nuclear criticality safety programs Metadata

Metadata describes a digital item, providing (if known) such information as creator, publisher, contents, size, relationship to other resources, and more. Metadata may also contain "preservation" components that help us to maintain the integrity of digital files over time.

Available Formats

Dublin Core: XML Dublin Core: JSON Dublin Core: Text Dublin Core: RDF/XML UNTL: XML Access METS: XML

Title

  • Main Title Nuclear data needs for application in nuclear criticality safety programs

Creator

  • Author: Leal, L. C.
    Creator Type: Personal
  • Author: Westfall, R. M.
    Creator Type: Personal
  • Author: Jordan, W. C.
    Creator Type: Personal
  • Author: Wright, R. Q.
    Creator Type: Personal
    Creator Info: Oak Ridge National Lab., TN (United States). Computational Physics and Engineering Div.

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, 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: 1995-09-01

Language

  • English

Description

  • Content Description: In nuclear criticality safety applications, a number of important uncertainties have to be addressed to establish the required criticality safety margin of a nuclear system. One source of these uncertainties is the basic nuclear data used to calculate the effective multiplication factor of the system. Before criticality safety calculations are performed, the bias and uncertainties of the codes and cross sections that are used must be determined. Cross-section data are measured, evaluated, and tested prior to their inclusion in nuclear data libraries. Traditionally, nuclear data evaluations are performed to support the analysis and design of thermal and fast reactors. The neutron spectra characteristic of the thermal and fast systems used for data testing are predominantly in the low- and high-energy ranges, with a relatively minor influence from the intermediate-energy range. In the area of nuclear criticality safety, nuclear systems involving spent fuel elements from reactors can lead to situations very different from those most commonly found in reactor analysis and design. These systems are not limited to thermal or fast neutron spectra and may have their most significant influence from the intermediate energy range. This requires extending the range of applicability of the nuclear data evaluation beyond thermal and fast systems. The aim here is to focus on the evaluated nuclear data pertaining to applications in nuclear criticality safety.
  • Physical Description: 10 p.

Subject

  • Keyword: Msre Reactor
  • Keyword: Criticality
  • Keyword: Fuel Cycle Centers
  • Keyword: Information Needs
  • STI Subject Categories: 99 Mathematics, Computers, Information Science, Management, Law, Miscellaneous
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Nuclear Data Collections
  • STI Subject Categories: 22 Nuclear Reactor Technology
  • Keyword: Uranyl Nitrates
  • Keyword: Safety Analysis
  • Keyword: Reactor Fueling
  • Keyword: Containers
  • Keyword: Evaluation
  • STI Subject Categories: 42 Engineering Not Included In Other Categories
  • Keyword: Uranium 233

Source

  • Conference: 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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: DE95017455
  • Report No.: CONF-9509100--15
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 102261
  • Archival Resource Key: ark:/67531/metadc623134

Note

  • Display Note: INIS; OSTI as DE95017455
Back to Top of Screen