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

Technical Report · Wed Feb 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/5052619· OSTI ID:5052619

Benedetti, R. L.; Lords, L. V.; Kiser, D. M.

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.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5052619
• Report Number(s): TREE-NUREG-1133
• Country of Publication: United States
• Language: English

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42 ENGINEERING
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ACCIDENTS
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FLOW BLOCKAGE
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FUEL ASSEMBLIES
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MATHEMATICAL MODELS
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REACTOR ACCIDENTS
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