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Analysis of institutional authors

Garcia-Herranz, N.AuthorCuervo, D.Author

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June 9, 2019
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A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides

Publicated to: ANNALS OF NUCLEAR ENERGY. 57 32-40 - 2013-07-01 57(), DOI: 10.1016/j.anucene.2013.01.039

Authors:

Ochoa, R; Vazquez, M; Alvarez-Velarde, F; Martin-Fuertes, F; Garcia-Herranz, N; Cuervo, D
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Affiliations

CIEMAT, Div Fis, Madrid, Spain - Author
Univ Politecn Madrid, Dept Ingn Nucl, E-28040 Madrid, Spain - Author

Abstract

Minor actinides (MM) transmutation is a main design objective of advanced nuclear systems such as generation IV Sodium Fast Reactors (SFRs). In advanced fuel cycles, MA contents in final high level waste packages are main contributors to short term heat production as well as to long-term radiotoxicity. Therefore, MA transmutation would have an impact on repository designs and would reduce the environment burden of nuclear energy. In order to predict such consequences Monte Carlo (MC) transport codes are used in reactor design tasks and they are important complements and references for routinely used deterministic computational tools. In this paper two promising Monte Carlo transport-coupled depletion codes, EVOLCODE and SERPENT, are used to examine the impact of MA burning strategies in a SFR core, 3600 MWth. The core concept proposal for MA loading in two configurations is the result of an optimization effort upon a preliminary reference design to reduce the reactivity insertion as a consequence of sodium voiding, one of the main concerns of this technology. The objective of this paper is double. Firstly, efficiencies of the two core configurations for MA transmutation are addressed and evaluated in terms of actinides mass changes and reactivity coefficients. Results are compared with those without MA loading. Secondly, a comparison of the two codes is provided. The discrepancies in the results are quantified and discussed. (C) 2013 Elsevier Ltd. All rights reserved.
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Keywords

Burnup calculationsHeterogeneous recycleHomogeneous recycleMinor actinide loadingMonte carlo-depletion codesReactivity coefficientsSodium fast reactors

Quality index

Bibliometric impact. Analysis of the contribution and dissemination channel

The work has been published in the journal ANNALS OF NUCLEAR ENERGY due to its progression and the good impact it has achieved in recent years, according to the agency Scopus (SJR), it has become a reference in its field. In the year of publication of the work, 2013, it was in position , thus managing to position itself as a Q1 (Primer Cuartil), in the category Nuclear Energy and Engineering. Notably, the journal is positioned above the 90th percentile.

From a relative perspective, and based on the normalized impact indicator calculated from World Citations provided by WoS (ESI, Clarivate), it yields a value for the citation normalization relative to the expected citation rate of: 1.03. This indicates that, compared to works in the same discipline and in the same year of publication, it ranks as a work cited above average. (source consulted: ESI Nov 13, 2025)

Specifically, and according to different indexing agencies, this work has accumulated citations as of 2026-04-26, the following number of citations:

  • WoS: 14
  • Scopus: 12
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Impact and social visibility

From the perspective of influence or social adoption, and based on metrics associated with mentions and interactions provided by agencies specializing in calculating the so-called "Alternative or Social Metrics," we can highlight as of 2026-04-26:

  • The use of this contribution in bookmarks, code forks, additions to favorite lists for recurrent reading, as well as general views, indicates that someone is using the publication as a basis for their current work. This may be a notable indicator of future more formal and academic citations. This claim is supported by the result of the "Capture" indicator, which yields a total of: 24 (PlumX).

It is essential to present evidence supporting full alignment with institutional principles and guidelines on Open Science and the Conservation and Dissemination of Intellectual Heritage. A clear example of this is:

  • Assignment of a Handle/URN as an identifier within the deposit in the Institutional Repository: https://oa.upm.es/21563/

As a result of the publication of the work in the institutional repository, statistical usage data has been obtained that reflects its impact. In terms of dissemination, we can state that, as of

  • Views: 424
  • Downloads: 869
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Leadership analysis of institutional authors

There is a significant leadership presence as some of the institution’s authors appear as the first or last signer, detailed as follows: First Author (Ochoa, R.) and Last Author (CUERVO GOMEZ, DIANA).

the author responsible for correspondence tasks has been Ochoa, R..

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Awards linked to the item

This work is partially funded by the EC Commission under the 7th EURATOM Framework Program, within the Collaborative Project CP-ESFR European Sodium Fast Reactor. In addition, authors would like to acknowledge the Spanish Consejo de Seguridad Nuclear for having partially funded this work and ENRESA also for its partial support in the frame of CIEMAT-ENRESA agreement.
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