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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 655 - 676 (22page)
이용수
초록· 키워드
오류제보하기
The first-ever integral effect test for simulating a guillotine break of a DVI (Direct Vessel Injection) line of the APR1400
was carried out with the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) from the same prototypic
pressure and temperature conditions as those of the APR1400. The major thermal hydraulic behaviors during a DVI line
break accident were identified and investigated experimentally. A method for estimating the break flow based on a balance
between the change in RCS inventory and the injection flow is proposed to overcome a direct break low measurement
deficiency. A post-test calculation was performed with a best-estimate safety analysis code MARS 3.1 to examine its prediction
capability and to identify any code deficiencies for the thermal hydraulic phenomena occurring during the DVI line break
accidents. On the whole, the prediction of the MARS code shows a good agreement with the measured data. However, the
code predicted a higher core level than did the data just before a loop seal clearing occurs, leading to no increase in the peak
cladding temperature. The code also produced a more rapid decrease in the downcomer water level than was predicted by the
data. These observable disagreements are thought to be caused by uncertainties in predicting countercurrent flow or condensation
phenomena in a downcomer region. The present integral effect test data will be used to support the present conservative
safety analysis methodology and to develop a new best-estimate safety analysis methodology for DVI line break accidents of
the APR1400.
목차
등록된 정보가 없습니다.
참고문헌 (20)
참고문헌 신청
/ 1995 / EPRI, “EPRI Utility Requirement Documents for the Advanced Light Water Reactor (Chapter 5),” (1995)
B. D. Chung / 2003 / Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break / The 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydr
B. J. Yun / 2003 / Experimental Observations of the Hydraulic Phenomena in the APR1400 Downcomer during the DVI Line Break Accident / Proc. of Korean Nuclear Society Spring Meeting
B. U. Bae / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / Proc. of ICAPP 2007
C.-H. Song / 2000 / Thermal Hydraulic Test Program for Evaluating or Verifying the Performance of New Design Features in KNGR / Proc. of Korean Nuclear Society Autumn Meeting
B. D. Chung / 2003 / Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break / The 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydr
B. J. Yun / 2003 / Experimental Observations of the Hydraulic Phenomena in the APR1400 Downcomer during the DVI Line Break Accident / Proc. of Korean Nuclear Society Spring Meeting
B. U. Bae / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / Proc. of ICAPP 2007
C.-H. Song / 2000 / Thermal Hydraulic Test Program for Evaluating or Verifying the Performance of New Design Features in KNGR / Proc. of Korean Nuclear Society Autumn Meeting
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