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Published: 2015-09-30
Abstract Views: 213
Views PDF: 32
DOI: https://doi.org/10.53747/jnst.v5i3.199
Issue
Vol. 5 No. 3 (2015)
Section
Articles
How to Cite
Do , N. D., & Phung , K. T. (2015). Using FRAPTRAN 1.5 code for safety evaluation of TVS-2006 fuel rod under transient conditions of VVER-1200 (AES-2006) reactor. Nuclear Science and Technology, 5(3), 44-55. https://doi.org/10.53747/jnst.v5i3.199

Using FRAPTRAN 1.5 code for safety evaluation of TVS-2006 fuel rod under transient conditions of VVER-1200 (AES-2006) reactor

Do Ngoc Diep1, Phung Khac Toan1
1 Vietnam Atomic Energy Agency, Vietnam 113 Tran Duy Hung, Cau Giay, Hanoi

Main Article Content

Abstract

This article shows the results of important thermal-mechanical parameters related to the TVS-2006 fuel rod design which were analyzed and evaluated by using FRAPTRAN1.5 code. Based on the data given in the Preliminary Safety Analysis Report (PSAR) of AES-2006 (Novovoronezh NPP-2 Power Unit No.1)and FRAP-T (Fuel Rod Analysis Program-Transient), FRAPTRAN1.5 calculations of TVS-2006 fuel rod behaviors in Loss of Coolant Accidents and Reactivity-Initiated Accidents conditions have been made. The calculated results related to safety criteria of fuel element and cladding temperatures, cladding stress and strain, fuel enthalpy, local oxide thickness, gap gas pressure, and elongation of fuel rod have been compared with the ones given in AES-2006 PSAR. A good agreement has been observed between AES-2006 PSAR andFRAPTRAN1.5 calculations.

Article Details

Keywords

Thermal-mechanical, fuel rod, LOCA, RIA, Safety evaluation, VVER, AES-2006

References

[1] K.J. Geelhood, W.G. Luscher, C.E. Beyer, J.M. Cuta, “FRAPTRAN 1.5: A Computer Code for the Transient Analysis of Oxide Fuel Rods”, NUREG/CR-7023, Vol.2 Rev.1 and PNNL-19400, Vol.2 Rev.1, Pacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352, 2014.
[2] K.J. Geelhood, W.G. Luscher and C.E. Beyer, “FRAPTRAN 1.5: Integral Assessment”, NUREG/CR-7022, Vol.2, US NRC, 2014.
[3] Federal Atomic Energy Agency, “Novovoronezh NPP-2 Power unit No.1: Preliminary Safety Analysis Report”, 2011.
[4] Jinzhao ZHANG, Zeynab UMIDOVA, Adrieu DETHIOUX, “Qualification of FRAPCON/FRAPTRAN codes for fuel rod design verification and fuel safety evaluation”, Transactions of the 2012 International Meeting on LWR Fuel Performance (TopFuel 2012), Manchester, UK, 2-5 September, 2012.
[5] Jimmy Sudjana, Zeynab Umidova, Jinzhao Zhang, Maxime Haedens and Christophe Schneidesch, "Evaluation of PWR Rod Ejection Accident Margins Using PANTHER/COBRA and FRAPTRAN," Proceedings of LWR Fuel Performance Meeting TopFuel 2013, Charlotte, NC, USA, September 15 - 19, 2013.