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Validation of trace code against ROSA/LSTF test for SBLOCA of pressure vessel upper-head small break
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2014 (English)In: 2013 21st International Conference on Nuclear Engineering, ICONE 2013: Volume 4: Thermal Hydraulics, ASME Press, 2014, Vol. 4Conference paper (Refereed)
Abstract [en]

OECD/NEA ROSA/LSTF project tests are performed on the Large Scale Test Facility (LSTF). LSTF is a full-height, fullpressure and 1/48 volumetrically-scaled two-loop system which aims to simulate Japanese Tsuruga-2 Westinghouse-type 4-loop PWR. ROSA-V Test 6-1 simulates a pressure vessel (PV) upper-head small break loss-of-coolant accident (SBLOCA) with a break size equivalent to 1.9% of the volumetrically scaled cross-sectional area of the reference PWR cold leg. By building a TRACE calculation model of LSTF and PV upper-head, the paper dedicated to assess the effect of different modeling options and parameters on simulating thermal hydraulic behaviors of TRACE code. The results show that TRACE code well reproduce the physical phenomena involved in this type of SBLOCA scenarios. Almost all the events in the experiment are well predicted by the model based on TRACE code. In addition, the sensitivity of different models and parameters are investigated. For example, the code slightly overestimated the break mass flow from upper head which could affect the accuracy of the results significantly. The rising of core exit temperature (CET) is significantly influenced by the bypass flow area between downcomer and hot leg.

Place, publisher, year, edition, pages
ASME Press, 2014. Vol. 4
Keyword [en]
LSTF, Safety analysis, SBLOCA, Thermal-hydraulics transient, TRACE
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Other Physics Topics
URN: urn:nbn:se:kth:diva-146955DOI: 10.1115/ICONE21-15548ISI: 000359512800042ScopusID: 2-s2.0-84901715630ISBN: 978-079185581-2OAI: diva2:726899
2013 21st International Conference on Nuclear Engineering, ICONE 2013; Chengdu; China; 29 July 2013 through 2 August 2013

QC 20140619

Available from: 2014-06-19 Created: 2014-06-18 Last updated: 2015-09-09Bibliographically approved

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Ma, Weimin
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Nuclear Power Safety
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