SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]

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The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-dimensional steady state solution scheme to initialize the flow field, (b) steady state and transient fuel rod conduction models, and (c) comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity ... continued below

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Pages: 322

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Benedetti, R. L.; Lords, L. V. & Kiser, D. M. February 1, 1978.

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Description

The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-dimensional steady state solution scheme to initialize the flow field, (b) steady state and transient fuel rod conduction models, and (c) comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage.

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Pages: 322

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Dep. NTIS, PC A14/MF A01.

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  • Report No.: TREE-NUREG-1133
  • Grant Number: EY-76-C-07-1570
  • DOI: 10.2172/5052619 | External Link
  • Office of Scientific & Technical Information Report Number: 5052619
  • Archival Resource Key: ark:/67531/metadc1056619

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Creation Date

  • February 1, 1978

Added to The UNT Digital Library

  • Jan. 22, 2018, 7:23 a.m.

Description Last Updated

  • June 8, 2018, 3:49 p.m.

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Benedetti, R. L.; Lords, L. V. & Kiser, D. M. SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR], report, February 1, 1978; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc1056619/: accessed June 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.