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Validation of trace code against ROSA/LSTF test for SBLOCA of pressure vessel upper-head small break
Vise andre og tillknytning
2014 (engelsk)Inngår i: 2013 21st International Conference on Nuclear Engineering, ICONE 2013: Volume 4: Thermal Hydraulics, ASME Press, 2014, Vol. 4Konferansepaper, Publicerat paper (Fagfellevurdert)
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.

sted, utgiver, år, opplag, sider
ASME Press, 2014. Vol. 4
Serie
PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING ; V004T09A042
Emneord [en]
LSTF, Safety analysis, SBLOCA, Thermal-hydraulics transient, TRACE
HSV kategori
Identifikatorer
URN: urn:nbn:se:kth:diva-146955DOI: 10.1115/ICONE21-15548ISI: 000359512800042Scopus ID: 2-s2.0-84901715630ISBN: 978-079185581-2 (tryckt)OAI: oai:DiVA.org:kth-146955DiVA, id: diva2:726899
Konferanse
2013 21st International Conference on Nuclear Engineering, ICONE 2013; Chengdu; China; 29 July 2013 through 2 August 2013
Merknad

QC 20140619

Tilgjengelig fra: 2014-06-19 Laget: 2014-06-18 Sist oppdatert: 2015-09-09bibliografisk kontrollert

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