A global approach to the physics validation of simulation codes for future nuclear systems

Palmiotti, G.; Salvatores, M.; Aliberti, G.; Hiruta, Hikaru; McKnight, R.D.; Obložinský, P.; Yang, Won Sik

doi:10.1016/j.anucene.2008.11.012

Cited by 27 publications

(16 citation statements)

References 8 publications

(4 reference statements)

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“…The cross section sensitivity coefficients are used to estimate the uncertainty of response parameter due to uncertain cross sections or to reduce the response parameter uncertainty by the use of integral experiment data. [89] VARI3D [90] is a generalized perturbation theory code that allows calculation of the effects on reactivity and reaction rate ratios of alterations in microscopic cross sections and/or material number densities. VARI3D is most frequently used to compute the reactivity coefficient distributions and kinetics parameters employed in reactor dynamics and safety analyses.…”

Section: Perturbation Theory and Uncertainty Analysis Codesmentioning

confidence: 99%

Fast Reactor Physics and Computational Methods

Yang¹

2012

Nuclear Engineering and Technology

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Section: Perturbation Theory and Uncertainty Analysis Codesmentioning

confidence: 99%

Fast Reactor Physics and Computational Methods

Yang¹

2012

Nuclear Engineering and Technology

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“…Table 3 illustrates the correlation factors among the different detector reaction rate slopes in the two experiments. These correlation factors are calculated using the sensitivity coefficients and covariance matrix used later in the adjustment step [12]. In fact the following equation is used:…”

Section: Na Consistent Data Assimilationmentioning

confidence: 99%

Consistent Data Assimilation of Structural Isotopes: 23Na and 56Fe

Palmiotti¹

2010

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iii SUMMARYA new approach is proposed, the consistent data assimilation, that allows to link the integral data experiment results to basic nuclear parameters employed by evaluators to generate ENDF/B point energy files in order to improve them. Practical examples are provided for the structural materials 23 Na and 56 Fe. The sodium neutron propagation experiments, EURACOS and JANUS-8, are used to improve via modifications of 23 Na nuclear parameters (like scattering radius, resonance parameters, Optical model parameters, Statistical Hauser-Feshbach model parameters, and Preequilibrium Exciton model parameters) the agreement of calculation versus experiments for a series of measured reaction rate detectors slopes. For the 56 Fe case the EURACOS and ZPR3 assembly 54 are used. Results have shown inconsistencies in the set of nuclear parameters used so that further investigation is needed. Future work involves comparison of results against a more traditional multigroup adjustments, and extension to other isotope of interest in the reactor community.

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“…The concept currently has wide use in fast breeder studies, and innovative reactor studies as well as in the field of criticality safety. In particular, it has gained recognition through dissemination by both the ORNL (Oak Ridge National Laboratory) group and the ANL (Argonne National Laboratory) group in the United States [11][12][13][14][15][16][17][18]. The representativity factor represents the amplitude of the similarity to a target system.…”

Section: Calculation Methods Of "Best Representativity"mentioning

confidence: 99%

Development of a “best representativity” method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility

Umano

Yoshioka

Obara

2014

Journal of Nuclear Science and Technology

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For nuclear critical experiments, it is essential to certify similarities of the experiment with the objective of the actual reactor conditions or actual reactor equipment. To judge the applicability of the experimental data, the concept of a "representativity factor" has recently been adopted in the critical experiment field, particularly for fast breeder reactors and future reactor studies. In this study, we extended this concept to the design of a light water reactor system. We developed a new numerical evaluation method and a calculation system. The method is based on a linear combination of the sensitivity coefficient vector of an experiment in which the representativity factor to the target system is maximized to utilize experimental data effectively. Simultaneously, using the measurement data of critical experiments, the method enables us to evaluate calculation errors caused by errors or uncertainties of physical parameters. The derivation of the new calculation method is explained first. We then qualify it with a sample calculation, presenting numerical results for three kinds of critical experiments conducted at the Toshiba Nuclear Critical Assembly facility. Finally, the results are compared with those of an extended bias factor method to clarify the performance of the new method.

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A global approach to the physics validation of simulation codes for future nuclear systems

Cited by 27 publications

References 8 publications

Fast Reactor Physics and Computational Methods

Fast Reactor Physics and Computational Methods

Consistent Data Assimilation of Structural Isotopes: 23Na and 56Fe

Development of a “best representativity” method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility

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