Comparison of TRAC and RELAP5 reactor system calculations for a DEGB LOCA in K-14. 1 Metadata

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Title

  • Main Title Comparison of TRAC and RELAP5 reactor system calculations for a DEGB LOCA in K-14. 1

Creator

  • Author: Griggs, D.P. (Westinghouse Savannah River Co., Aiken, SC (United States))
    Creator Type: Personal
  • Author: Liebmann, M.L. (Wais and Associates (United States))
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: DOE; USDOE, Washington, DC (United States)

Publisher

  • Name: Westinghouse Savannah River Company
    Place of Publication: Aiken, South Carolina

Date

  • Creation: 1990-09-01

Language

  • English

Description

  • Content Description: A comparison of TRAC and RELAP5 predictions of steady-state and DEGB LOCA results (FI phase) for K-14.1 has been made. Both codes had been previously benchmarked against 1985 L Reactor AC Flow data and were under configuration control. The purpose of the code-to-code comparison is to provide insight on the transient uncertainty in TRAC plenum and tank bottom plenum pressures. The comparisons focus on LOCA results between 0.5 and 2.0 s, which is the primary period of interest for Flow Instability (FI) limits.
  • Physical Description: Pages: (52 p)

Subject

  • Keyword: Heat Transfer
  • Keyword: Us Aec
  • Keyword: Reactor Accidents
  • STI Subject Categories: 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors
  • Keyword: Hydraulics
  • Keyword: Us Organizations 220900* -- Nuclear Reactor Technology-- Reactor Safety
  • Keyword: Reactor Cooling Systems
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: Computer Codes
  • Keyword: Comparative Evaluations
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Fluid Mechanics
  • Keyword: Us Doe
  • Keyword: Cooling Systems
  • Keyword: Accidents
  • Keyword: Production Reactors
  • Keyword: Reactors
  • Keyword: Mechanics
  • Keyword: Reactor Safety
  • STI Subject Categories: 990200 -- Mathematics & Computers
  • Keyword: Stability
  • Keyword: R Codes
  • Keyword: Energy Transfer
  • Keyword: T Codes
  • Keyword: Loss Of Coolant
  • Keyword: National Organizations
  • STI Subject Categories: 99 General And Miscellaneous//Mathematics, Computing, And Information Science
  • Keyword: Reactor Components
  • Keyword: Fluid Flow
  • Keyword: Us Erda
  • Keyword: Safety
  • Keyword: Savannah River Plant
  • Keyword: Evaluation

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: DE92015065
  • Report No.: WSRC-TR-90-393
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/5210353
  • Office of Scientific & Technical Information Report Number: 5210353
  • Archival Resource Key: ark:/67531/metadc1058731

Note

  • Display Note: OSTI; NTIS; INIS; GPO Dep.