Published 2014 | Version v1
Miscellaneous

Analysis of void fraction in single channel using TRACE, MARS-KS, and RELAP5

  • 1. KEPCO International Nuclear Graduate School (KINGS), Ulsan (Korea, Republic of)

Description

The accurate prediction of the void fraction is one of the most important factors in subchannel analyses. In general, the subchannel analysis has been conducted by means of dedicated subchannel analysis codes. However, the recent development of system codes with advanced two-phase flow model and three-dimensional components has helped more accurate and precise prediction of multiphase phenomena in nuclear reactor systems. This paper aims at evaluating the applicability of three different system codes to the prediction of the void fraction based on NUPEC experiment results employed for OECD/NRC PSBT benchmark. As a first step to the full scope analysis, analysis results for single channel experiments by using TRACE 5.0 Patch 3, MARS-KS 1.3, and RELAP5/MOD3.3 Patch 4 are presented in this paper. The result indicates that all codes slightly over-predict the void fraction compared to the experimental results in general and no significant discrepancies between the codes are observed. (author)

Part of:
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)

Additional details

Publishing Information

Imprint Title
Proceedings of the 10th international topical meeting on nuclear thermal hydraulics, operation and safety (NUTHOS-10)
Imprint Pagination
2846 p.
Journal Page Range
10 p.

Conference

Title
10. international topical meeting on nuclear thermal hydraulics, operation and safety
Acronym
NUTHOS-10
Dates
14-18 Dec 2014
Place
Ginowan, Okinawa (Japan)

Optional Information

Notes
Available as USB Flash Memory Data in PDF format. Paper ID: NUTHOS10-1089.pdf; 8 refs., 7 figs., 4 tabs.