Abstract
The object of this work is the validation and assessment of the TRACE v5.0 code using the scaled test ATLAS1 facility in the context of a DVI2 line break. In particular, the experiment selected models the 50%, 6-inch break of a DVI line. The same experiment was also adopted as a reference test in the ISP-503. The ISP-50 was proposed to, and accepted by, the OECD/NEA/CSNI due to its technical importance in the development of a best-estimate of safety analysis methodology for DVI line break accidents. In particular, the behavior of the two-phase flow in the upper annulus downcomer was expected to be complicated. What resulted was the need for relevant models to be implemented into safety analysis codes, in order to predict these thermal hydraulic phenomena correctly.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 719-726 |
| Number of pages | 8 |
| Journal | Nuclear Engineering and Technology |
| Volume | 44 |
| Issue number | 7 |
| DOIs | |
| State | Published - Oct 1 2012 |
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Keywords
- ATLAS facility
- DVI line break
- ISP-50
- Loop seal clearing
- Trace
ASJC Scopus subject areas
- Nuclear Energy and Engineering
Cite this
Trace V5 code application dvi line break loca using atlas facility. / Veronese, Fabio; Kozlowski, Tomasz.
In: Nuclear Engineering and Technology, Vol. 44, No. 7, 01.10.2012, p. 719-726.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Trace V5 code application dvi line break loca using atlas facility
AU - Veronese, Fabio
AU - Kozlowski, Tomasz
PY - 2012/10/1
Y1 - 2012/10/1
N2 - The object of this work is the validation and assessment of the TRACE v5.0 code using the scaled test ATLAS1 facility in the context of a DVI2 line break. In particular, the experiment selected models the 50%, 6-inch break of a DVI line. The same experiment was also adopted as a reference test in the ISP-503. The ISP-50 was proposed to, and accepted by, the OECD/NEA/CSNI due to its technical importance in the development of a best-estimate of safety analysis methodology for DVI line break accidents. In particular, the behavior of the two-phase flow in the upper annulus downcomer was expected to be complicated. What resulted was the need for relevant models to be implemented into safety analysis codes, in order to predict these thermal hydraulic phenomena correctly.
AB - The object of this work is the validation and assessment of the TRACE v5.0 code using the scaled test ATLAS1 facility in the context of a DVI2 line break. In particular, the experiment selected models the 50%, 6-inch break of a DVI line. The same experiment was also adopted as a reference test in the ISP-503. The ISP-50 was proposed to, and accepted by, the OECD/NEA/CSNI due to its technical importance in the development of a best-estimate of safety analysis methodology for DVI line break accidents. In particular, the behavior of the two-phase flow in the upper annulus downcomer was expected to be complicated. What resulted was the need for relevant models to be implemented into safety analysis codes, in order to predict these thermal hydraulic phenomena correctly.
KW - ATLAS facility
KW - DVI line break
KW - ISP-50
KW - Loop seal clearing
KW - Trace
UR - http://www.scopus.com/inward/record.url?scp=84871817544&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84871817544&partnerID=8YFLogxK
U2 - 10.5516/NET.02.2012.713
DO - 10.5516/NET.02.2012.713
M3 - Article
AN - SCOPUS:84871817544
VL - 44
SP - 719
EP - 726
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
SN - 1738-5733
IS - 7
ER -