A RETRAN02/MOD5 model was developed for Lungmen ABWR and applied for ATWS transient analysis. Three ATWS events including Main Steam Isolation Valve Closure (MSIVC), Loss of Offsite Power (LOOP), and Inadvertent Opening of all Turbine Bypass Valves (IOTBV) are analyzed in this study. During the first two transients, the vessel pressure is increased as a result of steam flow reduction due to the closure of main steam isolation valves (MSIVs) and Turbine Control Valves (TCVs) respectively. In the third transient, the vessel pressure is reduced because of the open of Turbine Bypass Valves (TBVs) and turns to be increased because of the closure of MSIVs. All of the above transients suffer high neutron flux as a result of void reduction. There are several equipments and procedures to mitigate ATWS transient such as feedwater trip, Reactor Internal Pumps (RIPs) runback and trip, and the depressurization of relief valves. After the ATWS high pressure signal is initiated and permissive for 180 seconds, Standby Liquid Control system is initiated to inject boron liquid into upper plenum to shutdown the reactor. The results conclude that equipments and procedures mitigate the event effectively and the core is brought to shutdown state.
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4816-7
PROCEEDINGS PAPER
Anticipated Transient Without Scram Analysis for an ABWR Using RETRAN
Chiung Wen Tsai,
Chiung Wen Tsai
National Tsing-Hua University, Hsinchu, Taiwan, R.O.C.
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Shu Ming Yang,
Shu Ming Yang
National Tsing-Hua University, Hsinchu, Taiwan, R.O.C.
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Chunkuan Shih,
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan, R.O.C.
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Jong-Rong Wang,
Jong-Rong Wang
Institute of Nuclear Energy Research, Lungtan, Taiwan, R.O.C.
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Shao Shih Ma,
Shao Shih Ma
Institute of Nuclear Energy Research, Lungtan, Taiwan, R.O.C.
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Su Chin Cheng
Su Chin Cheng
Taiwan Power Company, Taipei, Taiwan, R.O.C.
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Chiung Wen Tsai
National Tsing-Hua University, Hsinchu, Taiwan, R.O.C.
Shu Ming Yang
National Tsing-Hua University, Hsinchu, Taiwan, R.O.C.
Chunkuan Shih
National Tsing Hua University, Hsinchu, Taiwan, R.O.C.
Jong-Rong Wang
Institute of Nuclear Energy Research, Lungtan, Taiwan, R.O.C.
Shao Shih Ma
Institute of Nuclear Energy Research, Lungtan, Taiwan, R.O.C.
Su Chin Cheng
Taiwan Power Company, Taipei, Taiwan, R.O.C.
Paper No:
ICONE16-48732, pp. 775-781; 7 pages
Published Online:
June 24, 2009
Citation
Tsai, CW, Yang, SM, Shih, C, Wang, J, Ma, SS, & Cheng, SC. "Anticipated Transient Without Scram Analysis for an ABWR Using RETRAN." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Instrumentation and Controls. Orlando, Florida, USA. May 11–15, 2008. pp. 775-781. ASME. https://doi.org/10.1115/ICONE16-48732
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