Uncertainties in TRAC plenum pressures for the FI phase of a DEGB LOCA Metadata

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Title

  • Main Title Uncertainties in TRAC plenum pressures for the FI phase of a DEGB LOCA

Creator

  • Author: Griggs, D. P.
    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: 1991-05-01

Language

  • English

Description

  • Content Description: The TRAC-PF1/MOD1 code (TRAC) is used to perform best-estimate analyses of certain postulated Design Basis Accidents (DBAs) in SRS production reactors. Currently, the most limiting DBA in terms of reactor power level is an instantaneous double-ended guillotine break (DEGB) loss of coolant accident (LOCA). For this accident, TRAC is used to analyze only the first 5 seconds following the DEGB, which encompasses the Flow Instability (FI) phase of the DBA. The TRAC analysis provides time-dependent plenum and tank bottom pressures for use as boundary conditions in the FLOWTRAN code. The quantification of uncertainty is an important element of determining safe operating power levels for SRS reactors. A detailed methodology for the determination of uncertainty for the FI phase of a DEGB LOCA has been developed. This report presents estimates of the uncertainty in the time-dependent plenum pressures for the DEGB LOCA calculated by TRAC. The plenum pressure uncertainty was estimated by means of comparing TRAC results with steady-state data measured in L Reactor, and confirmed by comparisons with transient LOCA results calculated by an independent group with the RELAP5 code. An overview of the limits methodology is given and discusses the L Reactor data. The methodology for estimating the plenum pressure uncertainty is presented along with the results.
  • Physical Description: 56 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: F Codes
  • Keyword: Reactor Cooling Systems
  • STI Subject Categories: 22 General Studies Of Nuclear Reactors
  • Keyword: Computer Codes
  • STI Subject Categories: 21 Specific Nuclear Reactors And Associated Plants
  • Keyword: Data Covariances
  • Keyword: Fluid Mechanics
  • Keyword: Us Doe
  • Keyword: Cooling Systems
  • Keyword: Accidents
  • Keyword: Production Reactors
  • Keyword: Reactors
  • Keyword: Design Basis Accidents
  • Keyword: Safety
  • Keyword: Mechanics
  • Keyword: Reactor Safety
  • Keyword: L Reactor
  • STI Subject Categories: 990200 -- Mathematics & Computers
  • Keyword: Stability
  • Keyword: Savannah River Plant
  • Keyword: Energy Transfer
  • Keyword: T Codes
  • Keyword: Loss Of Coolant
  • Keyword: National Organizations
  • Keyword: Special Production Reactors
  • STI Subject Categories: 99 General And Miscellaneous//Mathematics, Computing, And Information Science
  • Keyword: Reactor Components
  • Keyword: Fluid Flow
  • Keyword: Us Erda
  • Keyword: Heavy Water Moderated Reactors
  • Keyword: Limiting Values
  • Keyword: R Codes

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: DE92015063
  • Report No.: WSRC-TR-90-263
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/5037132
  • Office of Scientific & Technical Information Report Number: 5037132
  • Archival Resource Key: ark:/67531/metadc1057760

Note

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