Comparisons of steady-state and transient thermal hydraulic results from SAS-DIF3DK and RELAP5 mod 3.2 for an RBMK reactor.

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The SAS-DIF3DK code couples a detailed 3-D neutron kinetics treatment with a detailed thermal hydraulics treatment. One goal of the work on SAS-DIF3DK is to produce a detailed code that will run a wide range of transients in real time. Achieving this goal will require efficient numerical methods and efficient coding, and it will probably require the use of multiple processors for larger problems. In order to obtain clean code-to-code thermal hydraulics comparisons with a recognized and established code, a detailed thermal hydraulic model was set up for an RBMK assembly and its associated piping, The same identical input model ... continued below

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16 p.

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Dunn, F. E. March 10, 1999.

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The SAS-DIF3DK code couples a detailed 3-D neutron kinetics treatment with a detailed thermal hydraulics treatment. One goal of the work on SAS-DIF3DK is to produce a detailed code that will run a wide range of transients in real time. Achieving this goal will require efficient numerical methods and efficient coding, and it will probably require the use of multiple processors for larger problems. In order to obtain clean code-to-code thermal hydraulics comparisons with a recognized and established code, a detailed thermal hydraulic model was set up for an RBMK assembly and its associated piping, The same identical input model was implemented in both SAS-DIF3DK and RELAP5 mod 3.2. Both steady-state and transient thermal hydraulics calculations were made with this model. Except for cladding temperatures in one transient, the SAS-DIF3DK results were similar to or almost identical to the RELAP5 results, and SAS-DIF3DK ran an order of magnitude or more faster than RELAP5. The cladding temperature differences can be explained in terms of different post-DNB models and heat transfer coefficients.

Physical Description

16 p.

Notes

INIS; OSTI as DE00012417

Medium: P; Size: 16 pages

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  • 9th Ninth International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 9), San Francisco, CA (US), 10/03/1999--10/08/1999

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  • Report No.: ANL/RA/CP-98562
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 12417
  • Archival Resource Key: ark:/67531/metadc627712

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  • March 10, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2017, 3:15 p.m.

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Dunn, F. E. Comparisons of steady-state and transient thermal hydraulic results from SAS-DIF3DK and RELAP5 mod 3.2 for an RBMK reactor., article, March 10, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc627712/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.