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Lin HT, Wang JR, Huang KC, Shih C, Chiang SC, Liu CC. Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.11.015] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Yang SM, Lin HT, Wang JR, Chen HC, Shih C, Chen SW. 3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions. KERNTECHNIK 2015. [DOI: 10.3139/124.110557] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
Lungmen nuclear power plant project started long time ago, it is not yet commercially operated but Taiwan Power Company has already prepared for its startup tests. 3RIP trip startup test is one of them. Three of the 10 RIPs will be manually tripped in the test. Response of the plant for this transient will be watched and recorded to check if the test criteria are satisfied. This paper is a result of code simulation of 3RIP trip startup test of Lungmen ABWR nuclear power plant. Thermal hydraulic code TRACE coupled with neutronics code PARCS were used to build the simulation model of Lungmen nuclear power plant. Startup tests under different plant power and flow conditions are considered in this research. A sensitivity study on the impact of different pump moment of inertia has been performed. Simulation results with TRACE and PARCS shows that the acceptance criteria for this startup test can be satisfied and the impact of different pump inertia is little.
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Affiliation(s)
- Shu-Ming Yang
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013 , Taiwan (R.O.C.)
| | - Hao-Tzu Lin
- Institute of Nuclear Energy Research , Atomic Energy Council, Executive Yuan, 1000 Wenhua Rd. Jiaan Village, Longtan District, Taoyuan City 32546 , Taiwan (R.O.C.)
| | - Jong-Rong Wang
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013 , Taiwan (R.O.C.)
| | - Hsiung-Chih Chen
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013 , Taiwan (R.O.C.)
| | - Chunkuan Shih
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013 , Taiwan (R.O.C.)
| | - Shao-Wen Chen
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., Hsin Chu 30013 , Taiwan (R.O.C.)
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Lin HT, Yang SM, Wang JR, Chen SW, Shih C. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant. KERNTECHNIK 2015. [DOI: 10.3139/124.110497] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
In this research, the TRACE/SNAP model of Lungmen ABWR nuclear power plant (NPP) has been established for the simulation and analysis of ultimate response guideline (URG). The main actions of URG are depressurization and low pressure water injection of reactor and containment venting. This research focuses to assess the URG utility of Lungmen NPP under Fukushima-like conditions. This study consists of three steps. The first step is the establishment of Lungmen NPP TRACE/SNAP model. In order to evaluate the system response of TRACE/SNAP model, FSAR data (MSIV closure and loss of feedwater flow transient) were used to compare with the results of TRACE. The second step is the URG simulation and analysis under Fukushima-like conditions by using Lungmen NPP TRACE/SNAP model. In this step, the no URG case was also performed in order to evaluate the URG effectiveness of Lungmen NPP. In order to confirm the mechanical property and integrity of fuel rods, the final step is FRAPTRAN analysis. According to TRACE analysis results, the URG can keep the peak cladding temperature (PCT) below the criteria 1 088.7 K under Fukushima-like conditions which indicates that Lungmen NPP can be controlled in a safe situation. Nevertheless, if Lungmen NPP does not perform the URG under Fukushima-like conditions, the water level may drop lower than TAF after 1 100 s which means a safety issue about the fuel rods may be generated. The analysis results of FRAPTRAN also indicate the integrity of fuel rods cannot be kept under the above conditions.
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Affiliation(s)
- H.-T. Lin
- Institute of Nuclear Energy Research , Atomic Energy Council, Executive Yuan, 1000 Wenhua Rd. Jiaan Village, Longtan District, Taoyuan City 32546, Taiwan (R.O.C) , E-mail:
| | - S.-M. Yang
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013 , Taiwan (R.O.C.)
| | - J.-R. Wang
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013 , Taiwan (R.O.C.)
| | - S.-W. Chen
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013 , Taiwan (R.O.C.)
| | - C. Shih
- Institute of Nuclear Engineering and Science , National Tsing Hua University, No. 101, Section 2, Kuang Fu Rd., HsinChu 30013 , Taiwan (R.O.C.)
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