지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2008.1
- 수록면
- 199 - 212 (14page)
이용수
초록· 키워드
오류제보하기
A small-break loss of coolant accident (SB-LOCA) test with a break size equivalent to a 3-inch cold leg break of the
APR1400 was carried out as the first transient integral effect test using the ATLAS (Advanced Thermal-hydraulic Test Loop
for Accident Simulation). This was the first integral effect test to investigate the integral performance of the test facility and
to verify its simulation capability for one of the design-basis accidents. Reasonably good thermal hydraulic data was
obtained so that an integral performance of the fluid sub-systems was identified and control performance of the ATLAS was
confirmed under real thermal hydraulic conditions. Based on the measured data, a post-test calculation was carried out using
the best-estimate thermal hydraulic safety analysis code, MARS 3.1, and the similarity between the expected and actual data
was investigated. On the whole, the post-test calculation reasonably predicts the major thermal hydraulic parameters
measured during the SB-LOCA test. The obtained data will be used to enhance the simulation capability of the ATLAS and
to improve an input model of the ATLAS for simulation of other target scenarios.
목차
등록된 정보가 없습니다.
참고문헌 (14)
참고문헌 신청
/ 2004 / MARS Code Manual Volume I: Code Structure, System Models, and Solution Methods
B. J. Yun / 2005 / Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow / The 11th Int. Topical Meeting on Nuclear Reactor Thermal- Hydra
B. U. Bae / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / ICAPP ’07
H. S. Park / 2007 / Calculation Sheet for the Basic Design of the ATLAS Fluid System
I. C. Chu / 2007 / Development of Passive Flow Controlling Safety Injection Tank for APR1400 / Nuclear Engineering and Design 238 (200)
B. J. Yun / 2005 / Development of an Average Bidirectional Flow Tube for a Measurement of the Single and Two Phase Flow / The 11th Int. Topical Meeting on Nuclear Reactor Thermal- Hydra
B. U. Bae / 2007 / Integral Experiment and RELAP5 Analysis for DVI line Break SBLOCA in APR1400 / ICAPP ’07
H. S. Park / 2007 / Calculation Sheet for the Basic Design of the ATLAS Fluid System
I. C. Chu / 2007 / Development of Passive Flow Controlling Safety Injection Tank for APR1400 / Nuclear Engineering and Design 238 (200)
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
LBLOCA AND DVI LINE BREAK TESTS WITH THE ATLAS INTEGRAL FACILITY
Nuclear Engineering and Technology
2009 .01
-
Second ATLAS Domestic Standard Problem (DSP-02) for a Code Assessment
Nuclear Engineering and Technology
2013 .01
-
An Experimental Study on a LBLOCA Reflood Phase of the APR1400 Using the ATLAS
대한기계학회 춘추학술대회
2008 .05
-
APR1400 모의를 위한 ATLAS 안전주입탱크의 주입 성능에 관한 특성 시험
에너지공학
2008 .06
-
EXPERIMENTAL SIMULATION OF A DIRECT VESSEL INJECTION LINE BREAK OF THE APR1400 WITH THE ATLAS
Nuclear Engineering and Technology
2009 .01
-
FIRST ATLAS DOMESTIC STANDARD PROBLEM (DSP-01)FOR THE CODE ASSESSMENT
Nuclear Engineering and Technology
2011 .01
-
APR1400 모의를 위한 ATLAS 장치의 안전주입탱크 주입성능에 관한 실험
한국에너지학회 학술발표회
2007 .11
-
연구 현장 - ATLAS 운영 현황과 향후 전망
원자력산업
2015 .01
-
SPACE 코드를 이용한 ATLAS 주급수관 파단 사고 해석
한국에너지학회 학술발표회
2012 .04
-
ATLAS 모든 교류전원상실 실험에 대한 SPACE 코드 사고대처 방안 분석
대한기계학회 춘추학술대회
2017 .06
-
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
-
SPACE 기반 SBLOCA 최적평가를 위한 ATLAS 실험의 124회 SRS 계산
한국에너지학회 학술발표회
2016 .04
-
TRACE V5 CODE APPLICATION DVI LINE BREAK LOCA USING ATLAS FACILITY
Nuclear Engineering and Technology
2012 .01
-
A SUMMARY OF 50th OECD/NEA/CSNI INTERNATIONAL STANDARD PROBLEM EXERCISE (ISP-50)
Nuclear Engineering and Technology
2012 .01
-
ATLAS 실험장치의 새로운 RPV에 대한 자연순환 특성 실험
한국유체기계학회 학술대회 논문집
2017 .12
-
SEPARATE AND INTEGRAL EFFECT TESTS FOR VALIDATION OF COOLING AND OPERATIONAL PERFORMANCE OF THE APR+ PASSIVE AUXILIARY FEEDWATER SYSTEM
Nuclear Engineering and Technology
2012 .01
-
MAJOR THERMAL-HYDRAULIC PHENOMENA FOUND DURING ATLAS LBLOCA REFLOOD TESTS FOR AN ADVANCED PRESSURIZED WATER REACTOR APR1400
Nuclear Engineering and Technology
2011 .01
-
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
-
INTERNATIONAL STANDARD PROBLEM 50: THE UNIVERSITY OF PISA CONTRIBUTION
Nuclear Engineering and Technology
2012 .01
이 논문의 저자 정보
최근 본 자료
댓글(0)
0