Thermal Analysis of Irradiation Experiments in the ATR 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 Thermal Analysis of Irradiation Experiments in the ATR

Creator

  • Author: Murray, Paul
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of Nuclear Energy, Science, and Technology.
    Contributor Type: Organization
    Contributor Info: DOE - NE

Publisher

  • Name: Idaho National Laboratory
    Place of Publication: Idaho Falls, Idaho
    Additional Info: Idaho National Laboratory (INL)

Date

  • Creation: 2012-09-01

Language

  • English

Description

  • Content Description: Reactor material testing in the INL's Advanced Test Reactor (ATR) involves modeling and simulation of each experiment to accurately determine the irradiation temperature. This paper describes thermal analysis of capsule experiments using gas gap temperature control and provides data on recent material tests that validate the modeling results. Static capsule experiments and lead-out capsule experiments are discussed. The source of temperature variation in capsule experiments and ways to mitigate these variations are also explained. Two examples of instrumented lead-out capsule experiments, TMIST-1 and UCSB-2, are presented. A comparison of measured and calculated temperatures is used to validate the thermal models and to ascertain the accuracy of the calculated temperature.

Subject

  • Keyword: Thermal Analysis
  • Keyword: Advanced Test Reactor
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants Advanced Test Reactor
  • Keyword: Irradiation Experiments

Source

  • Conference: Test, Research, and Training Reactors Annual Meeting,San Diego, CA,09/24/2012,09/27/2012

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

  • Report No.: INL/CON-12-26307
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 1057691
  • Archival Resource Key: ark:/67531/metadc836821
Back to Top of Screen