Browse > Article
http://dx.doi.org/10.5516/NET.02.2012.708

A SUMMARY OF 50th OECD/NEA/CSNI INTERNATIONAL STANDARD PROBLEM EXERCISE (ISP-50)  

Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Baek, Won-Pil (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Kang, Kyoung-Ho (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Cho, Seok (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Kim, Yeon-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.44, no.6, 2012 , pp. 561-586 More about this Journal
Abstract
This paper describes a summary of final prediction results by system-scale safety analysis codes during the OECD/NEA/CSNI ISP-50 exercise, targeting a 50% Direct Vessel Injection (DVI) line break integral effect test performed with the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS). This ISP-50 exercise has been performed in two consecutive phases: "blind" and "open" phases. Quantitative comparisons were performed using the Fast Fourier Transform Based Method (FFTBM) to compare the overall accuracy of the collected calculations. Great user effects resulting from the combination of the possible reasons were found in the blind phase, confirming that user effect is still one of the major issues in connection with the system thermal-hydraulic code application. Open calculations showed better prediction accuracy than the blind calculations in terms of average amplitude (AA) value. A total of nineteen organizations from eleven countries participated in this ISP-50 program and eight leading thermal-hydraulic system analysis codes were used: APROS, ATHLET, CATHARE, KORSAR, MARS-KS, RELAP5/MOD3.3, TECH-M-97, and TRACE.
Keywords
ISP-50; ATLAS; DVI line break; SB-LOCA; APR1400;
Citations & Related Records

Times Cited By Web Of Science : 0  (Related Records In Web of Science)
연도 인용수 순위
  • Reference
1 M. Ishii and I. Kataoka, "Similarity Analysis and Scaling Criteria for LWRs Under Single Phase and Two-Phase Natural Circulation," NUREG/CR-3267, ANL-83-32, Argonne National Laboratory (1983).
2 K.Y. Choi, Y. S. Kim, C.-H. Song, and W. P. Baek, "Major Achievements and Prospect of the ATLAS Integral Effect Tests," Science and Technology of Nuclear Installations, Volume 2012, Article ID 375070, doi:10.1155/2012/375070, (2012).
3 K. Y. Choi, H. S. Park, S. Cho, K. H. Kang, N. H. Choi, W. P. Baek, and Y. S. Kim, "Effects of Break Size on Direct Vessel Injection Line Break Accidents of the ATLAS," Nuclear Technology, 175, 604, (2011).
4 K. H. Kang, S. K. Moon, H. S. Park, S. Cho, K.Y. Choi, B. J. Yun, T. S. Kwon, S. J. Yi, C. K. Park, B. D. Kim, Y. S. Kim, C.-H. Song, and W. P. Baek, "Detailed Description Report of ATLAS Facility and Instrumentation," KAERI/TR-4316/2011 (2011).
5 OECD/NEA, "Re-Analysis of the ISP-13 Exercise, Post Test Analysis of the LOFT L2-5 Test Calculation, "BEMUSE PHASE II Report, NEA/CSNI/R(2006)2 (2005).
6 F. D'Auria, M. Leonardi, R. Pochard, "Methodology for the evaluation of thermal hydraulic codes accuracy," Proc. Int. Conf. on New trends in Nuclear System Thermohydraulics, Pisa, 467-477 (1994).
7 A. Prosek, F. D'Auria, and B. Mavko, "Review of Quantitative Accuracy Assessments with Fast Fourier Transform Based Method (FFTBM)," Nuclear Engineering and Design, 217, 179, (2002).   DOI   ScienceOn
8 R. F. Kunz, G. F. Kasmala, J. H. Mahaffy, C. J. Murray, "On the automated assessment of nuclear reactor systems code accuracy," Nuclear Engineering and Design, 211, Issues 2-3, 245, (2002).   DOI
9 B.D. Chung et al., "Phenomena Identification and Ranking Tabulation for APR1400 Direct Vessel Injection Line Break," The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9, (2003).
10 W. P. Baek, C.-H. Song, B. J. Yun, T. S. Kwon, S. K. Moon and S. J. Lee, "KAERI Integral Effect Test Program and the ATLAS Design," Nuclear Technology, 152, 183 (2005).
11 W. P. Baek and Y. S. Kim, "Accident Simulation ATLAS for APWRs," Nuclear Engineering International, 53, 21 (2008).
12 EPRI, "EPRI Utility Requirement Documents for the Advanced Light Water Reactor (Chapter 5)," (1995).
13 K. Y. Choi, W. P. Baek, S. Cho, H.S. Park, K.H. Kang, Y.S. Kim and H. T. Kim, "OECD/NEA/CSNI International Standard Problem No. 50, Final Integration Report," Volume 1 -3, NEA/CSNI/R(2012)6.