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# Thermal Hydraulic and Fuel Rod Mechanical Combination Analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP Interface (NUREG/IA-0477)

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## Publication Information

**Manuscript Completed:** February 2016**Date Published:** November 2016

**Prepared by:**Jong-Rong Wang*, Chunkuan Shih*, Hao-Chun Chang*, Shao-Wen Chen*, Show-Chyuan Chiang**,Tzu-Yao Yu**

*Institute of Nuclear Engineering and Science, National Tsing Hua University; Nuclear and NewEnergy Education and Research Foundation101 Section 2, Kuang Fu Rd., HsinChu, Taiwan

**Department of Nuclear Safety, Taiwan Power Company242, Section 3, Roosevelt Rd., Zhongzheng District, Taipei, Taiwan

K. Tien, NRC Project Manager

Division of Systems AnalysisOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

**Prepared as part of:**The Agreement on Research Participation and Technical ExchangeUnder the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

**Published by:**U.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

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## Abstract

After the measurement uncertainty recapture power uprates, Kuosheng nuclear power plant (NPP) was uprated the power from 2894 MWt to 2943 MWt. For this power upgrade, several analysis codes were applied to assess the safety of Kuosheng Nuclear Power Plant. In our group, there were a lot of effort on thermal hydraulic code, TRACE, had been done before. However, to enhance the reliability and confidence of these transient analyses, thermal hydraulic code, RELAP5/MOD3.3 will be applied in the future. The main work of this research is to establish a RELAP5/MOD3.3 model of Kuosheng NPP with SNAP interface. Model establishment of RELAP5 code is referred to the Final Safety Analysis Report (FSAR), training documents, and TRACE model which has been developed and verified before. After completing the model establishment, three startup test scenarios would be applied to the RELAP5 model. With comparing the startup test data and TRACE model analysis results, the applicability of RELAP5 model would be assessed.

Recently, Taiwan Power Company is concerned in stretch power uprated plan and uprates the power to 3030 MWt. Before the stretch power uprates, several transient analyses should be done for ensuring that the power plant could maintain stability in higher power operating conditions. In this research, three overpressurization transients scenario including main steam isolation valves closure, turbine trip with bypass failure and load rejection with bypass failure would be performed by RELAP5 MOD3.3 code. Further, the thermal hydraulic properties of the reactor core will be transferred as the boundary conditions of FRAPTRAN code. With the boundary conditions from RELAP5 code, the fuel rod mechanical properties during the transient could be determined. In this research, the SNAP interface is applied so that the transferring process between RELAP5 and FRAPTRAN code can be completed automatically with Python Job Stream. That is, the researchers need not calculate and transfer the thermal hydraulic boundary conditions for FRAPTRAN analysis manually.

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