Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods

Sánchez-Saez, Francisco; Alberola, Sofía Carlos; Sancho, M. T.; Martorell, Sebastián

doi:10.1016/j.nucengdes.2017.04.037

Cited by 21 publications

(7 citation statements)

References 19 publications

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“…The pioneering BEPU methodology was code scaling, applicability, and uncertainty (CSAU) [8], sponsored by the USNRC, where the propagation of uncertainty to the results was performed using a surrogate model of the thermo-hydraulic code, namely a polynomial response surface. Around the turn of the century, a new type of propagation procedure gained acceptance, based on the original code and on the calculation of tolerance limits using nonparametric Wilks' method [9,10]. A method called advanced statistical treatment of uncertainty method (ASTRUM) is one of the typical methodologies based on Wilks' theory.…”

Section: Bepu Methodsmentioning

confidence: 99%

BEPU Analysis in LBLOCA Safety Review Calculation

Sun

Wang

et al. 2021

Sustainability

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Deterministic safety analysis (DSA) is essential for nuclear power plant licensing. The conservative method followed CFR50 Appendix K, which will lead to a large margin. As one of the DSA methodologies, best estimate plus uncertainty (BEPU) generates more realistic results that can be used in the license application of nuclear power plants (NPPs). However, uncertainty evaluation of parameters is needed in BEPU. In this article, the safety regulatory focuses on the large break loss of coolant accident (LBLOCA) of an advanced PWR. The BEPU analysis is mainly performed by TRACE V5.0 patch 4 code, and the uncertainty analysis is conducted based on DAKOTA code. For correlation coefficients analysis, the sample size is enlarged reasonably. According to the results, this NPP meets the acceptance criteria effectively in LBLOCA with enough margin. By statistic assessment, the set of PCTs calculated has typical normal distribution characters. Based on BEPU, the uncertainties of parameters are studied. Additionally, the influence of sample size on the correlation of parameters is considered too. It could be seen that more samples could permit a more accurate estimation for Spearman partial correlation coefficient (abbreviated as SPCC). The conclusions of this article can provide technical support for the subsequent review of the safety analysis report and the design changes of NPPs.

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Section: Bepu Methodsmentioning

confidence: 99%

BEPU Analysis in LBLOCA Safety Review Calculation

Sun

Wang

et al. 2021

Sustainability

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“…This work mainly researches the uncertainty of input parameters, and their distributions are determined through PIRT and related literature research (Zhujian and Shoulv, 1992;Gupta et al, 2013;Sanchez-Saez et al, 2017). 9.…”

Section: Reference the Phenomena Identification And Rankingmentioning

confidence: 99%

“…Many researchers used the BEPU method to analyze SBLOCA. Sanchez-Saez et al (2017) presented a methodology and the application to G7.1 experiment. They performed uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks' and GAM surrogate methods and found that for larger sample sizes, GAMPE and Wilks' results present similar performance.…”

Section: Introductionmentioning

confidence: 99%

“…Although some progress has been made on the SBLOCA uncertainty analysis of NPPs, the previous research still has some imperfections. In the process of researching the uncertainties and sensitivities of the input parameters, many scholars usually first studied the uncertainties and then carried out a sensitivity analysis (Perez et al, 2011;Gupta et al, 2013;Ghione et al, 2017;Sanchez-Saez et al, 2017;Wang et al, 2017Wang et al, , 2019Sanchez-Saez et al, 2018). This order can share the same set of sampling parameters, which saves the sampling cost.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

An Improved Best Estimate Plus Uncertainty Method for Small-Break Loss-of-Coolant Accident in Pressurized Water Reactor

Sun

Zhang

et al. 2020

Front. Energy Res.

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Best estimate plus uncertainty (BEPU) analysis method has been widely used to analyze various transient accidents of pressurized water reactor (PWR). However, the traditional BEPU method has some limitations: (1) The input parameters are not clearly defined, resulting in inaccurate conclusions in the sensitivity analysis. (2) The uncertainty quantification and sensitivity analysis usually share the same set of samples, but they have different requirements for the sample size. In this work, an improved BEPU method is proposed, which can alleviate the above defects. The improved BEPU method possesses the following two characteristics: (1) The sensitivity analysis is performed for the steady-state and transient calculation, respectively. It provides more comprehensive results than does the traditional BEPU method. (2) The sensitivity analysis is performed before the uncertainty analysis to reduce the number of uncertainty analysis inputs. A small-break loss-of-coolant accident (SBLOCA) is simulated by Reactor Excursion and Leak Analysis Program (RELAP) 5 to verify the accuracy and applicability of the improved BEPU method. By the sensitivity analysis, the coolant pump inlet roughness, main flow rate, core heat channel temperature, break area, and PRZ pressure have moderate or higher relationships with the peak core outlet temperature. The fission product yield factor has a moderate positive relationship with the peak cladding temperature (PCT). The sensitivity analysis by the improved BEPU method shows that the peak core outlet temperature has strong relationships with main flow rate, core heat channel temperature, and PRZ pressure, which is not captured by the traditional BEPU method. As a result, it is more reasonable to take steady-state parameters as inputs in the sensitivity analysis of transient. Only those parameters with high correlation coefficients are sampled for uncertainty analysis. Meanwhile, the results of the uncertainty analysis obtained by the improved BEPU are consistent with the results of the traditional method. Neither the PCT nor the peak core outlet temperature will exceed their limits. The results illustrate that the improved BEPU method can reduce the size of samples but maintains the desired accuracy.

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“…Therefore, uncertainty analysis was performed to find the key parameters affecting the system performance, research the uncertainty propagation rules, and evaluate the precision of codes. Uncertainty analysis has been widely used in the field of nuclear engineerings, such as system simulation, 23‐25 multidimensional CFD, 21,26‐29 and reactor physics calculation 30,31 …”

Section: Introductionmentioning

confidence: 99%

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

Cheng

Zhang

et al. 2020

Int J Energy Res

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Summary The passive residual heat removal system (PRHRS) is of great significance to ensure the safety of small modular reactors. In this work, a PRHRS based on the reactor pressure vessel was designed and optimized for the lead‐bismuth reactor SVBR‐100 and an one‐dimensional transient analysis code transient analysis codes for LBE reactor was developed as well. The uncertainty analysis was carried out to identify and optimize the key parameters affecting PRHRS, based on the one‐dimensional physical fields obtained from the primary loop and evaporator. The results of transient calculation showed that the designed PRHRS can effectively remove the heat of the core under the accident of unprotected loss of flow and the station blackout (SBO). The results of sensitivity analysis showed that the maximum temperature of lead‐bismuth eutectic (LBE) was strongly positively correlated with heat capacity and thermal conductivity of the cladding, and was moderately positively correlated with the kinetic coefficient of the pump; The medium negative correlation factor of peak pellet temperature (PPT), peak cladding temperature (PCT), and maximum LBE temperature was the diameter of the sleeve of PRHRS, and therefore, increasing the diameter of the sleeve can improve the performance of the system. The results of uncertainty quantification showed that the output uncertainties of PPT and PCT were larger than those inputs. The uncertainty of LBE temperature was very low, and all thermal parameters in SBO were within safe limits. Finally, the optimized parameters of PRHRS were obtained. This work can provide a reference for the development of designing PRHRS and relevant transient calculation codes for small modular LBE reactors.

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Uncertainty analysis of PKL SBLOCA G7.1 test simulation using TRACE with Wilks and GAM surrogate methods

Cited by 21 publications

References 19 publications

BEPU Analysis in LBLOCA Safety Review Calculation

BEPU Analysis in LBLOCA Safety Review Calculation

An Improved Best Estimate Plus Uncertainty Method for Small-Break Loss-of-Coolant Accident in Pressurized Water Reactor

Design and optimization of passive residual heat removal system for lead‐bismuth reactorSVBR‐100

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