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논문 기본 정보

자료유형
학술저널
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저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제49권 제1호
발행연도
2017.1
수록면
54 - 70 (17page)

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The accumulator is a passive safety injection device for emergency core cooling systems. As an important safety feature for providing a high-speed injection flow to the core by compressed nitrogen gas pressure during a loss-of-coolant accident (LOCA), the accumulator injects its precharged nitrogen into the system after its coolant has been emptied. Attention has been drawn to the possible negative effects caused by such a nitrogen injection in passive safety nuclear power plants. Although some experimental work on the nitrogen injection has been done, there have been no comparative tests in which the effects on the system responses and the core safety have been clearly assessed. In this study, a new thermal hydraulic integral test facilitydthe advanced core-cooling mechanism experiment (ACME)dwas designed and constructed to support the CAP1400 safety review. The ACME test facility was used to study the nitrogen injection effects on the system responses to the small break loss-of-coolant accident LOCA (SBLOCA) transient. Two comparison test groupsda 2-inch cold leg break and a double-ended direct-vessel-injection (DEDVI) line breakdwere conducted. Each group consists of a nitrogen injection test and a nitrogen isolation comparison test with the same break conditions. To assess the nitrogen injection effects, the experimental data that are representative of the system responses and the core safety were compared and analyzed. The results of the comparison show that the effects of nitrogen injection on system responses and core safety are significantly different between the 2-inch and DEDVI breaks. The mechanisms of the different effects on the transient were also investigated. The amount of nitrogen injected, along with its heat absorption, was likewise evaluated in order to assess its effect on the system depressurization process. The results of the comparison and analyses in this study are important for recognizing and understanding the potential negative effects on the passive core cooling performance caused by nitrogen injection during the SBLOCA transient.
#Accumulator #Nitrogen gas #Core cooling #Passive safety #Small break

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참고문헌 (27)

참고문헌 신청
[학 google schola D.C. Sun / 2015 / Experimental investigation of upper plenum entrainment in AP1000 / Prog. Nucl. Energy 80 : 80 ~ 85 google schola G.E. Wilson / 1998 / The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis / Nucl. Eng. Des 186 : 23 ~ google schola H.J. Chang / 2012 / A new integral test facility ACME for passive safety PWR / ANS Winter Meeting google schola J. N. Reyes Jr. / 1999 / Final report of NRC AP600 research conducted at Oregon State University google schola

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