Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code

Markku Hänninen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

1 Citation (Scopus)

Abstract

At the moment the two-fluid system code APROS has CCFL (Counter Current Flow Limitation) correlations that are designed only for a single pipe or for bundle geometry. In the reactor pressure vessel the downcomer and the upper tie plate of the core are components that call for special CCFL correlations. In the present task the Glaeser CCFL correlations for a downcomer and an upper tie plate have been implemented in the code. The implemented correlations have been validated by calculating several downcomer and upper tie plate test cases of the UPTF (Upper Plenum Test Facility). In the tests the steam flow, the emergency core cooling flows, injection locations and the pressure levels were varied. In the validation the UPTF facility has been modeled with a nodalization, which is normally used in the corresponding calculations. Because the calculation results do not depend merely on the CCFL correlations the new Kutateladze coefficients of the Glaeser correlation had to be specified during the validation. With the selected coefficients, good, slightly conservative results were obtained. In the paper the work done with the correlations and the results of the validation calculations are described.
Original languageEnglish
Title of host publicationProceedings of the 16th International Conference on Nuclear Engineering, ICONE16
Place of PublicationFlorida
PublisherAmerican Society of Mechanical Engineers ASME
Pages153-162
ISBN (Print)0-7918-4816-7, 978-0-7918-4816-6
Publication statusPublished - 2008
MoE publication typeA4 Article in a conference publication
Event16th International Conference on Nuclear Engineering, ICONE-16 - Orlando, Florida, United States
Duration: 11 May 200815 May 2008

Conference

Conference16th International Conference on Nuclear Engineering, ICONE-16
Abbreviated titleICONE16
CountryUnited States
CityOrlando, Florida
Period11/05/0815/05/08

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Fluids
Test facilities
Pressure vessels
Steam
Pipe
Cooling
Geometry

Cite this

Hänninen, M. (2008). Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code. In Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16 (pp. 153-162). Florida: American Society of Mechanical Engineers ASME.
Hänninen, Markku. / Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code. Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. Florida : American Society of Mechanical Engineers ASME, 2008. pp. 153-162
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abstract = "At the moment the two-fluid system code APROS has CCFL (Counter Current Flow Limitation) correlations that are designed only for a single pipe or for bundle geometry. In the reactor pressure vessel the downcomer and the upper tie plate of the core are components that call for special CCFL correlations. In the present task the Glaeser CCFL correlations for a downcomer and an upper tie plate have been implemented in the code. The implemented correlations have been validated by calculating several downcomer and upper tie plate test cases of the UPTF (Upper Plenum Test Facility). In the tests the steam flow, the emergency core cooling flows, injection locations and the pressure levels were varied. In the validation the UPTF facility has been modeled with a nodalization, which is normally used in the corresponding calculations. Because the calculation results do not depend merely on the CCFL correlations the new Kutateladze coefficients of the Glaeser correlation had to be specified during the validation. With the selected coefficients, good, slightly conservative results were obtained. In the paper the work done with the correlations and the results of the validation calculations are described.",
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Hänninen, M 2008, Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code. in Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. American Society of Mechanical Engineers ASME, Florida, pp. 153-162, 16th International Conference on Nuclear Engineering, ICONE-16, Orlando, Florida, United States, 11/05/08.

Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code. / Hänninen, Markku.

Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. Florida : American Society of Mechanical Engineers ASME, 2008. p. 153-162.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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AB - At the moment the two-fluid system code APROS has CCFL (Counter Current Flow Limitation) correlations that are designed only for a single pipe or for bundle geometry. In the reactor pressure vessel the downcomer and the upper tie plate of the core are components that call for special CCFL correlations. In the present task the Glaeser CCFL correlations for a downcomer and an upper tie plate have been implemented in the code. The implemented correlations have been validated by calculating several downcomer and upper tie plate test cases of the UPTF (Upper Plenum Test Facility). In the tests the steam flow, the emergency core cooling flows, injection locations and the pressure levels were varied. In the validation the UPTF facility has been modeled with a nodalization, which is normally used in the corresponding calculations. Because the calculation results do not depend merely on the CCFL correlations the new Kutateladze coefficients of the Glaeser correlation had to be specified during the validation. With the selected coefficients, good, slightly conservative results were obtained. In the paper the work done with the correlations and the results of the validation calculations are described.

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Hänninen M. Implementation and validation of downcomer and upper tie plate CCFL correlations in a two-fluid code. In Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. Florida: American Society of Mechanical Engineers ASME. 2008. p. 153-162