Nuclear Energy for New Europe 2009

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No: 213

Conference: Nuclear Energy for New Europe 2009

Title: Animation of RELAP5 Reference Calculations for Krško Full Scope Simulator Validation

Theme: Thermal Hydraulics

Author(s): Andrej Prošek, Borut Mavko

Contact : Andrej Prošek

E-mail: andrej.prosek@ijs.si

Address: Institut "Jožef Stefan" R4
1001 Ljubljana

Country: Slovenia

The Krško nuclear power plant (NPP), which is a two-loop pressurized water reactor, Westinghouse type, before modernization in 2000 obtained plant specific full scope simulator. With the RELAP5/MOD2 computer code reference calculations of some design basis accidents were performed for the verification of Krško Full Scope Simulator. In 2004 annual ANSI/ANS validation was performed using RELAP5/MOD3.3 computer code. The purpose of the present analyses was to reanalyse reference calculations for KFSS validation with the aim to animate the calculations. Namely, this will help to better understand the physical phenomena and processes and more efficiently interpret the results obtained using the complex best-estimate thermalhydraulic codes. The new reference calculations were performed with the latest RELAP5/MOD3.3 Patch03 code. For animations the Symbolic Nuclear Analysis Package (SNAP) version 1.1 was used. In total six scenarios were analyzed: two scenarios of the Small Break Loss-of-Coolant Accident (LOCA), two scenarios of the Loss of Main Feedwater (LOFW), scenario of the Anticipated Transient Without Scram (ATWS), and scenario of the Steam Generator Tube Rupture (SGTR). Animation schemes were created for the primary and secondary system, a reactor vessel, a pressurizer with pressurizer relief tank, main steamline, a steam generator, main feedwater, an emergency core cooling system and an auxiliary feedwater system. Besides, the reactor protection systems signals and time sequence of events were added for better understanding of the transient progression. The developed animation model of Krško nuclear power plant showed several benefits like better understanding of the calculated physical phenomena and processes, user friendly tool for understanding the nodalization and the detail of plant modelling, better presentation of the results due to visualization and movies, a convenient tool to train new users of thermal-hydraulic code etc. It can also be concluded that such modern tool attracts young people to work also with system codes comparing to the last decade when most favour computational fluid dynamics codes.

No:	213
Conference:	Nuclear Energy for New Europe 2009
Title:	Animation of RELAP5 Reference Calculations for Krško Full Scope Simulator Validation
Theme:	Thermal Hydraulics
Author(s):	Andrej Prošek, Borut Mavko
Contact :	Andrej Prošek
E-mail:	andrej.prosek@ijs.si
Address:	Institut "Jožef Stefan" R4 1001 Ljubljana
Country:	Slovenia

The Krško nuclear power plant (NPP), which is a two-loop pressurized water reactor, Westinghouse type, before modernization in 2000 obtained plant specific full scope simulator. With the RELAP5/MOD2 computer code reference calculations of some design basis accidents were performed for the verification of Krško Full Scope Simulator. In 2004 annual ANSI/ANS validation was performed using RELAP5/MOD3.3 computer code. The purpose of the present analyses was to reanalyse reference calculations for KFSS validation with the aim to animate the calculations. Namely, this will help to better understand the physical phenomena and processes and more efficiently interpret the results obtained using the complex best-estimate thermalhydraulic codes. The new reference calculations were performed with the latest RELAP5/MOD3.3 Patch03 code. For animations the Symbolic Nuclear Analysis Package (SNAP) version 1.1 was used. In total six scenarios were analyzed: two scenarios of the Small Break Loss-of-Coolant Accident (LOCA), two scenarios of the Loss of Main Feedwater (LOFW), scenario of the Anticipated Transient Without Scram (ATWS), and scenario of the Steam Generator Tube Rupture (SGTR). Animation schemes were created for the primary and secondary system, a reactor vessel, a pressurizer with pressurizer relief tank, main steamline, a steam generator, main feedwater, an emergency core cooling system and an auxiliary feedwater system. Besides, the reactor protection systems signals and time sequence of events were added for better understanding of the transient progression. The developed animation model of Krško nuclear power plant showed several benefits like better understanding of the calculated physical phenomena and processes, user friendly tool for understanding the nodalization and the detail of plant modelling, better presentation of the results due to visualization and movies, a convenient tool to train new users of thermal-hydraulic code etc. It can also be concluded that such modern tool attracts young people to work also with system codes comparing to the last decade when most favour computational fluid dynamics codes.