The two-phase system analysis code MARS [1] has been used for the uncertainty quantification of NEPTUN reflood test [2] analysis. By performing 10,000 calculations based on a random variation of the MARS model parameters and measured data, a mean value, and the 95% upper bounds are traced along the number of calculations. The CPU-intensive calculations were performed using the 11 node PC-cluster under Linux platform. The Monte-Carlo calculation results suggest a total number of 2,000 calculations would be sufficient to determine the stable mean and 95% upper bound values. The peak temperatures predictions are also used to find the 95% bounding values by using the Wilks’ method. For the 1st order one-sided formula, every 59 peak temperatures are examined to locate the bounding temperature, with a 95% confidence. The 2nd and 3rd order values were found in a similar way. The uncertainty band by the Wilks’ formula, when compared with the true 95% bounding value, is observed to be quite broad, especially in the case of the 1st order. The 2nd or 3rd orders or a full Monte-Carlo method would be necessary to demonstrate that the safety of the plant is ensured with a sufficient margin. A supplementary sensitivity study, for the nine uncertain parameters selected for the NEPTUN analysis, is also performed to find the degree of influence of each parameter on the peak rod temperature.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4243-6
PROCEEDINGS PAPER
Uncertainty Quantification of NEPTUN Analysis Using Wilks’ Formula With an Extended Number of Calculations Available to Purchase
Moonkyu Hwang,
Moonkyu Hwang
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Young-Jin Lee,
Young-Jin Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Bub-Dong Chung
Bub-Dong Chung
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Moonkyu Hwang
Korea Atomic Energy Research Institute, Daejeon, Korea
Young-Jin Lee
Korea Atomic Energy Research Institute, Daejeon, Korea
Bub-Dong Chung
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE14-89419, pp. 429-436; 8 pages
Published Online:
September 17, 2008
Citation
Hwang, M, Lee, Y, & Chung, B. "Uncertainty Quantification of NEPTUN Analysis Using Wilks’ Formula With an Extended Number of Calculations." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 2: Thermal Hydraulics. Miami, Florida, USA. July 17–20, 2006. pp. 429-436. ASME. https://doi.org/10.1115/ICONE14-89419
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
A Probabilistic Approach for Electric Vehicle Battery Risk Estimation Based on a Safe Operating Area
J. Electrochem. En. Conv. Stor (November,2025)
Quantifying Uncertainty in Multiscale Heat Conduction Calculations
J. Heat Transfer (November,2014)
Posterior Covariance Matrix Approximations
J. Verif. Valid. Uncert (March,2024)
Related Chapters
Advances in the Stochastic Modeling of Constitutive Laws at Small and Finite Strains
Advances in Computers and Information in Engineering Research, Volume 2
Developing Human Performance Measures (PSAM-0207)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
A Bayesian Approach to Setting Equipment Performance Criteria (PSAM-0438)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)