Method and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files: Major findings of the NEA WPEC Subgroup 39

Salvatores, M.; Palmiotti, G.

doi:10.1051/epjconf/202023913001

Cited by 16 publications

(13 citation statements)

References 19 publications

(23 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Massimo has published many papers on this methodology (among them [7,52,55,58]). It is through his leadership role on the WPEC Subgroup 33 [59], Subgroup 39 [65], and Subgroup 46 that he initiated a younger generation of reactor physicists to the usefulness of this methodology. One important point always enlightened by Massimo is the role of the experimental correlation in the adjustment [62].…”

Section: Methodologies For Exploiting Integral Experiments For Neutronics Reactor Design Validationmentioning

confidence: 99%

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems

Palmiotti

Blaise

Mellier

2021

EPJ Nuclear Sci. Technol.

Self Cite

View full text Add to dashboard Cite

Among the many domains of reactor physics on which Massimo Salvatores gave his considerable contributions, he was particularly passionate about integral experiments. In this paper, we make a review of selected experimental campaigns among the numerous ones he has promoted, conceived, designed, directed, or analyzed. They have been regrouped in a temporal sequence corresponding to the different periods of Massimo's career, which exceeded 50 years. When possible, for each of the experiments we provide a brief description, the goal for which it was conceived and carried out, and the practical impact on validation and design improvement. Finally, the conclusions offer thoughts and suggestions for the future of the integral experiments and a possible way of honoring the invaluable legacy that Massimo Salvatores has left to us.

show abstract

Section: Methodologies For Exploiting Integral Experiments For Neutronics Reactor Design Validationmentioning

confidence: 99%

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems

Palmiotti

Blaise

Mellier

2021

EPJ Nuclear Sci. Technol.

Self Cite

View full text Add to dashboard Cite

show abstract

“…However, estimating reliable correlations requires a detailed uncertainty analysis that is time-intensive. As a starting point, WPEC SG-33 [36] covariances could be used.…”

Section: Adjustmentmentioning

confidence: 99%

Understanding the impact of nuclear-data covariances on various integral responses using adjustment

Neudecker

Grosskopf²,

Alwin³

et al. 2023

EPJ Web Conf.

View full text Add to dashboard Cite

The EUCLID (Experiments Underpinned by Computational Learning for Improvements in Nuclear Data) project created a library of sensitivities for nine different integral responses with respect to nuclear data. These integral responses were obtained from measurements at LLNL (Lawrence Livermore National Laboratory) pulsed spheres, critical and sub-critical assemblies. At the same time, covariances for ENDF/B-VIII.0 were processed at LANL (Los Alamos National Laboratory). The combination of these data allow us to study the impact of nuclear-data covariances on various integral responses, either by forward-propagating covariances via sensitivities, or by using nuclear data, integral responses, and sensitivities for adjustment. Here, we will present: the impact of 1H, 9Be, 12C, 27Al, 56Fe, 235,238U, and 239,240Pu ENDF/B-VIII.0 covariances on simulated bounds of the following integral responses: LLNL pulsed-spheres neutron-leakage spectra, the effective neutron multiplication factor, reaction rates, and reactivity coefficients of ICSBEP critical assemblies. Also, adjustment results with the same nuclear-data covariances and responses will be discussed. LA-UR-22-31309

show abstract

“…These activities started mainly from the viewpoint of improving the target accuracy of nuclear reactors. After that, activities were handed over to SG39 and SG46 [23,24], and methodology for effectively utilizing the cross-section adjustment method for nuclear data evaluation and validation were also examined.…”

Section: Introductionmentioning

confidence: 99%

Development of adjusted nuclear data library for fast reactor application

Yokoyama

2023

EPJ Web Conf.

View full text Add to dashboard Cite

In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s. The adjusted library is called the unified cross-section set, which is an ABBN-type group constant set with 70-group energy structure. The first version was developed in 1991 and is called ADJ91. After that, ADJ98, ADJ2000, ADJ2000R, and ADJ2010 were constantly developed. For instance, ADJ2010 was developed based on JENDL-4.0, which provides covariance data needed to apply the cross-section adjustment method, by using 488 integral experimental data acquired in typical fast reactor systems. ADJ2010 has been used as the standard cross-section set for nuclear design in the fast reactor cycle technology development project (FaCT) and the succeeding fast reactor projects. In parallel, the integral experimental data were further expanded to improve the design prediction accuracy of the core loaded with MA and/or degraded Pu. Using the additional integral experimental data, development of the next version of ADJ2017 was started in 2017. In 2022, the latest unified cross-section set AJD2017R was developed based on JENDL-4.0 by using 619 integral experimental data. An overview of the latest version with a review of previous ones will be shown. On the other hand, the latest Japanese evaluated nuclear data library JENDL-5 was released at the end of 2021. In the development of JENDL-5, some of the integral experimental data used in ADJ2017R were explicitly utilized in the nuclear data evaluation. However, this is not reflected in the covariance data. This situation needs to be considered when developing a next version of the unified cross-section set based on JENDL-5. Preliminary adjustment calculation based on JENDL-5 is performed using C/E (calculation/experiment) values simply evaluated by a sensitivity analysis. The preliminary result of the JENDL-5-based adjustment will be also discussed.

show abstract

Method and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files: Major findings of the NEA WPEC Subgroup 39

Cited by 16 publications

References 19 publications

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems

Massimo Salvatores: integral experiments and their use for the validation of nuclear data and the neutronic design of advanced nuclear systems

Understanding the impact of nuclear-data covariances on various integral responses using adjustment

Development of adjusted nuclear data library for fast reactor application

Contact Info

Product

Resources

About