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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 775 - 784 (10page)
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초록· 키워드
오류제보하기
This paper summarizes the tests performed in the ATLAS facility during its first two years of operation (2007~2008).
Two categories of tests have been performed successfully: (a) the reflood phase of the large-break loss-of-coolant accidents
in a cold leg, and (b) the breaks in one of four direct vessel injection lines. Those tests contributed to understanding the
unique thermal-hydraulic behavior, resolving the safety-related concerns and providing an evaluation of the safety analysis
codes and methodology for the advanced pressurized water reactor, APR1400. Several important and interesting phenomena
have been observed during the tests. In most cases, the ATLAS shows reasonable accident characteristics and conservative
results compared with those predicted by one-dimensional safety analysis codes. A wide variety of small-break LOCA tests
will be performed in 2009.
목차
등록된 정보가 없습니다.
참고문헌 (14)
참고문헌 신청
/ 1995 / EPRI (1995), “EPRI Utility Requirement Documents for the Advanced Light Water Reactor (Chapter 5).”
Bae, B. U. / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / Proc. of ICAPP 2007
Baek, W.P. / 2005 / KAERI Integral Effect Test Program and the ATLAS Design / Nucl. Technol. 152 (2) : 183 ~ 195
Baek, W.P. / 2008 / Accident Simulation ATLAS for APWRs / Nucl. Eng. Int. 53 (646) : 21 ~ 25
Choi, K.Y. / 2005 / Simulation Capability of the ATLAS Facility for Major Design Basis Accidents / Nucl. Technol. 156 (3) : 199 ~ 212
Bae, B. U. / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / Proc. of ICAPP 2007
Baek, W.P. / 2005 / KAERI Integral Effect Test Program and the ATLAS Design / Nucl. Technol. 152 (2) : 183 ~ 195
Baek, W.P. / 2008 / Accident Simulation ATLAS for APWRs / Nucl. Eng. Int. 53 (646) : 21 ~ 25
Choi, K.Y. / 2005 / Simulation Capability of the ATLAS Facility for Major Design Basis Accidents / Nucl. Technol. 156 (3) : 199 ~ 212
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An Experimental Study on a LBLOCA Reflood Phase of the APR1400 Using the ATLAS
대한기계학회 춘추학술대회
2008 .05
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INTEGRAL BEHAVIOR OF THE ATLAS FACILITY FOR A 3-INCH SMALL BREAK LOSS OF COOLANT ACCIDENT
Nuclear Engineering and Technology
2008 .01
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EXPERIMENTAL SIMULATION OF A DIRECT VESSEL INJECTION LINE BREAK OF THE APR1400 WITH THE ATLAS
Nuclear Engineering and Technology
2009 .01
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APR1400 모의를 위한 ATLAS 안전주입탱크의 주입 성능에 관한 특성 시험
에너지공학
2008 .06
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Second ATLAS Domestic Standard Problem (DSP-02) for a Code Assessment
Nuclear Engineering and Technology
2013 .01
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TRACE V5 CODE APPLICATION DVI LINE BREAK LOCA USING ATLAS FACILITY
Nuclear Engineering and Technology
2012 .01
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MAJOR THERMAL-HYDRAULIC PHENOMENA FOUND DURING ATLAS LBLOCA REFLOOD TESTS FOR AN ADVANCED PRESSURIZED WATER REACTOR APR1400
Nuclear Engineering and Technology
2011 .01
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APR1400 모의를 위한 ATLAS 장치의 안전주입탱크 주입성능에 관한 실험
한국에너지학회 학술발표회
2007 .11
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FIRST ATLAS DOMESTIC STANDARD PROBLEM (DSP-01)FOR THE CODE ASSESSMENT
Nuclear Engineering and Technology
2011 .01
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SPACE 코드를 이용한 ATLAS 주급수관 파단 사고 해석
한국에너지학회 학술발표회
2012 .04
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ANALYSIS OF THE ISP-50 DIRECT VESSEL INJECTION SBLOCA IN THE ATLAS FACILITY WITH THE RELAP5/MOD3.3 CODE
Nuclear Engineering and Technology
2012 .01
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CORE THERMAL HYDRAULIC BEHAVIOR DURING THE REFLOOD PHASE OF COLD-LEG LBLOCA EXPERIMENTS USING THE ATLAS TEST FACILITY
Nuclear Engineering and Technology
2009 .01
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연구 현장 - ATLAS 운영 현황과 향후 전망
원자력산업
2015 .01
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ATLAS 모든 교류전원상실 실험에 대한 SPACE 코드 사고대처 방안 분석
대한기계학회 춘추학술대회
2017 .06
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INTERNATIONAL STANDARD PROBLEM 50: THE UNIVERSITY OF PISA CONTRIBUTION
Nuclear Engineering and Technology
2012 .01
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Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design
Nuclear Engineering and Technology
2017 .01
-
AN EXPERIMENTAL STUDY WITH SNUF AND VALIDATION OF THE MARS CODE FOR A DVI LINE BREAK LOCA IN THE APR1400
Nuclear Engineering and Technology
2009 .01
-
MARS 코드를 이용한 ATLAS 모든 교류전원상실 실험 민감도 분석
대한기계학회 춘추학술대회
2017 .06
-
The MARS Simulation of the ATLAS Main Steam Line Break Experiment
에너지공학
2014 .12
-
A SUMMARY OF 50th OECD/NEA/CSNI INTERNATIONAL STANDARD PROBLEM EXERCISE (ISP-50)
Nuclear Engineering and Technology
2012 .01
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