Faster-than-real-time simulation of nuclear reactor accidents: the TRAC-NPA code

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A reactor safety code that provides faster-than-real-time capabilities greatly enhances the effectiveness of an analyst. We have developed a new version of the Transient Reactor Analysis Code, TRAC-NPA, which is capable of running many one- and three-dimensional transients faster than real time on current computers. TRAC is an Eulerian finite-difference code designed to model transient, two-phase, multidimensional, steam-water flow in nuclear reactors. TRAC-NPA is fast running both because it employs the efficient stability-enhancing two-step (SETS) numerical method and because much of the coding is vectorized. TRAC-NPA has been coupled to an interactive graphics executive to create a version of the … continued below

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11 pages

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Woodruff, S.B. April 1, 1985.

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Description

A reactor safety code that provides faster-than-real-time capabilities greatly enhances the effectiveness of an analyst. We have developed a new version of the Transient Reactor Analysis Code, TRAC-NPA, which is capable of running many one- and three-dimensional transients faster than real time on current computers. TRAC is an Eulerian finite-difference code designed to model transient, two-phase, multidimensional, steam-water flow in nuclear reactors. TRAC-NPA is fast running both because it employs the efficient stability-enhancing two-step (SETS) numerical method and because much of the coding is vectorized. TRAC-NPA has been coupled to an interactive graphics executive to create a version of the Nuclear Plant Analyzer. The features of the executive include instantaneous user-friendly display of calculational results, replay, restart with parameter variation, and interactive simulation of operator actions. The graphics executive thus provides an interface that can further enhance the effectiveness of an analyst when the underlying safety code provides faster-than-real-time simulation.

Physical Description

11 pages

Notes

NTIS, PC A02/MF A01 - GPO.

Source

  • Cray science and engineering symposium, Bloomington, MN, USA, 14 Apr 1985

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  • Other: TI85010710
  • Report No.: LA-UR-85-1264
  • Report No.: CONF-8504123-1
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5573762
  • Archival Resource Key: ark:/67531/metadc1085692

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • April 1, 1985

Added to The UNT Digital Library

  • Feb. 10, 2018, 10:06 p.m.

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  • June 20, 2019, 2:58 p.m.

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Woodruff, S.B. Faster-than-real-time simulation of nuclear reactor accidents: the TRAC-NPA code, article, April 1, 1985; New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1085692/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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