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Title: Verification of the Calore Thermal Analysis Code.


Abstract not provided.

Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
Report Number(s):
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: Proposed for presentation at the Tri-Laboratory Engineering Conference held May 7-10, 2007 in Ablquerque, NM.
Country of Publication:
United States

Citation Formats

Dowding, Kevin J., and Ben Blackwell. Verification of the Calore Thermal Analysis Code.. United States: N. p., 2007. Web.
Dowding, Kevin J., & Ben Blackwell. Verification of the Calore Thermal Analysis Code.. United States.
Dowding, Kevin J., and Ben Blackwell. Fri . "Verification of the Calore Thermal Analysis Code.". United States. doi:.
title = {Verification of the Calore Thermal Analysis Code.},
author = {Dowding, Kevin J. and Ben Blackwell},
abstractNote = {Abstract not provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 01 00:00:00 EDT 2007},
month = {Fri Jun 01 00:00:00 EDT 2007}

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  • Calore is the ASC code developed to model steady and transient thermal diffusion with chemistry and dynamic enclosure radiation. An integral part of the software development process is code verification, which addresses the question 'Are we correctly solving the model equations'? This process aids the developers in that it identifies potential software bugs and gives the thermal analyst confidence that a properly prepared input will produce satisfactory output. Grid refinement studies have been performed on problems for which we have analytical solutions. In this talk, the code verification process is overviewed and recent results are presented. Recent verification studies havemore » focused on transient nonlinear heat conduction and verifying algorithms associated with (tied) contact and adaptive mesh refinement. In addition, an approach to measure the coverage of the verification test suite relative to intended code applications is discussed.« less
  • The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provides a best-estimate prediction of the response of light water reactors or test facilities to postulated accident sequences. One of the features of the code is the ability to analyze the vessel and its heated core in three dimensions. The code is being used to analyze the results of tests in a large-scale reflood test facility built in Japan, known as the Cylindrical Core Test Facility (CCTF). Two test runs have been analyzed that are useful for verification of the three-dimensional analysis capability of the TRAC code.more » One test began with an initial temperature skew across the heated core. The second test had a large radial power skew between the central and peripheral assemblies. The good agreement between the calculation and the experiment for both of these experiments demonstrates the three-dimensional analysis capability of the TRAC code.« less
  • Predicted performance during both steady state and transient reactor operation determines the steady state operating limits on LMFBRs. Unnecessary conservatism in performance predictions will not contribute to safety, but will restrict the reactor to more conservative, less economical steady state operation. The most general method for reducing analytical conservatism in LMFBR's without compromising safety is to develop, validate and apply more sophisticated computer models to the limiting performance analyses. The purpose of the on-going Natural Circulation Verification Program (NCVP) is to develop and validate computer codes to analyze natural circulation transients in LMFBRs, and thus, replace unnecessary analytical conservatism withmore » demonstrated calculational capability.« less
  • No abstract prepared.