Open Access
RELAP5-3D User Problems
Richard Allan Riemke
- 01 Sep 2002
TL;DR: This presentation will discuss some of the more generic user problems that have been reported on RELAP5-3D as well as their resolution.
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Abstract: The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The 3D capability in RELAP5-3D includes 3D hydrodynamics2 and 3D neutron kinetics3,4. Assessment, verification, and validation of the 3D capability in RELAP5-3D is discussed in the literature5,6,7,8,9,10. Additional assessment, verification, and validation of the 3D capability of RELAP5-3D will be presented in other papers in this users seminar. As with any software, user problems occur. User problems usually fall into the categories of input processing failure, code execution failure, restart/renodalization failure, unphysical result, and installation. This presentation will discuss some of the more generic user problems that have been reported on RELAP5-3D as well as their resolution.
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References
An assessment of RELAP5-3D using the Edwards-O'Brien Blowdown problem
E. T. Tomlinson,D. L. Aumiller +1 more
- 01 Jul 1999
TL;DR: In this article, the RELAP5-3D standard installation problem based on the Edwards-O'Brien Blowdown Test was modified to model the appropriate initial conditions and to represent the proper location of the instruments present in the experiment.
A New Assessment of RELAP5-3D Using a General Electric Level Swell Problem
TL;DR: The RELAP5-3D (version bt) computer program was used to assess a General Electric level swell experiment as mentioned in this paper, and the results of this study show that the default RELAP 5-3-D interfacial drag package compares most favorably with the experimental data.
Assessment of RELAP5-3D multi-dimensional component model using data from LOFT Test L2-5
C.B. Davis
- 01 Jul 1998
TL;DR: The capability of the RELAP5-3D computer code to perform multi-dimensional analysis of a pressurized water reactor (PWR) was assessed using data from the Loss-of-Fluid Test (LOFT) L2-5 experiment as mentioned in this paper.
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