Decay heat uncertainty quantification of MYRRHA

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Decay heat uncertainty quantification of MYRRHA. / Fiorito, Luca; Buss, O.; Hoefer, A.; Stankovskiy, Alexey; Van den Eynde, Gert.

EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. Vol. 146 2017. ed. 2017. p. 1-4 09021 (EPJ Web of Conferences).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paperpeer-review

Harvard

Fiorito, L, Buss, O, Hoefer, A, Stankovskiy, A & Van den Eynde, G 2017, Decay heat uncertainty quantification of MYRRHA. in EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. 2017 edn, vol. 146, 09021, EPJ Web of Conferences, pp. 1-4, 2016 - ND, Bruges, Belgium, 2016-09-11. https://doi.org/10.1051/epjconf/201714609021

APA

Fiorito, L., Buss, O., Hoefer, A., Stankovskiy, A., & Van den Eynde, G. (2017). Decay heat uncertainty quantification of MYRRHA. In EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology (2017 ed., Vol. 146, pp. 1-4). [09021] (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714609021

Vancouver

Fiorito L, Buss O, Hoefer A, Stankovskiy A, Van den Eynde G. Decay heat uncertainty quantification of MYRRHA. In EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. 2017 ed. Vol. 146. 2017. p. 1-4. 09021. (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714609021

Author

Fiorito, Luca ; Buss, O. ; Hoefer, A. ; Stankovskiy, Alexey ; Van den Eynde, Gert. / Decay heat uncertainty quantification of MYRRHA. EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. Vol. 146 2017. ed. 2017. pp. 1-4 (EPJ Web of Conferences).

Bibtex - Download

@inproceedings{c1ee8e4ccfe5473f9836424d91dd04ea,
title = "Decay heat uncertainty quantification of MYRRHA",
abstract = "MYRRHA is a lead-bismuth cooled MOX-fueled accelerator driven system (ADS) currently in the design phase at SCK•CEN in Belgium. The correct evaluation of the decay heat and of its uncertainty level is very important for the safety demonstration of the reactor. In the first part of this work we assessed the decay heat released by the MYRRHA core using the ALEPH-2 burnup code. The second part of the study focused on the nuclear data uncertainty and covariance propagation to the MYRRHA decay heat. Radioactive decay data, independent fission yield and cross section uncertainties/covariances were propagated using two nuclear data sampling codes, namely NUDUNA and SANDY. According to the results, 238U cross sections and fission yield data are the largest contributors to the MYRRHA decay heat uncertainty. The calculated uncertainty values are deemed acceptable from the safety point of view as they are well within the available regulatory limits.",
keywords = "Decay Heat, uncertainty, sensitivity, depletion",
author = "Luca Fiorito and O. Buss and A. Hoefer and Alexey Stankovskiy and {Van den Eynde}, Gert",
note = "Score=3; 2016 - ND : International Conference on Nuclear Data for Science and Technology, ND2016 ; Conference date: 11-09-2016 Through 16-09-2016",
year = "2017",
month = sep,
day = "18",
doi = "10.1051/epjconf/201714609021",
language = "English",
volume = "146",
series = "EPJ Web of Conferences",
publisher = "EDP Sciences",
pages = "1--4",
booktitle = "EPJ Web of Conferences",
edition = "2017",
url = "http://www.nd2016.eu/",

}

RIS - Download

TY - GEN

T1 - Decay heat uncertainty quantification of MYRRHA

AU - Fiorito, Luca

AU - Buss, O.

AU - Hoefer, A.

AU - Stankovskiy, Alexey

AU - Van den Eynde, Gert

N1 - Score=3

PY - 2017/9/18

Y1 - 2017/9/18

N2 - MYRRHA is a lead-bismuth cooled MOX-fueled accelerator driven system (ADS) currently in the design phase at SCK•CEN in Belgium. The correct evaluation of the decay heat and of its uncertainty level is very important for the safety demonstration of the reactor. In the first part of this work we assessed the decay heat released by the MYRRHA core using the ALEPH-2 burnup code. The second part of the study focused on the nuclear data uncertainty and covariance propagation to the MYRRHA decay heat. Radioactive decay data, independent fission yield and cross section uncertainties/covariances were propagated using two nuclear data sampling codes, namely NUDUNA and SANDY. According to the results, 238U cross sections and fission yield data are the largest contributors to the MYRRHA decay heat uncertainty. The calculated uncertainty values are deemed acceptable from the safety point of view as they are well within the available regulatory limits.

AB - MYRRHA is a lead-bismuth cooled MOX-fueled accelerator driven system (ADS) currently in the design phase at SCK•CEN in Belgium. The correct evaluation of the decay heat and of its uncertainty level is very important for the safety demonstration of the reactor. In the first part of this work we assessed the decay heat released by the MYRRHA core using the ALEPH-2 burnup code. The second part of the study focused on the nuclear data uncertainty and covariance propagation to the MYRRHA decay heat. Radioactive decay data, independent fission yield and cross section uncertainties/covariances were propagated using two nuclear data sampling codes, namely NUDUNA and SANDY. According to the results, 238U cross sections and fission yield data are the largest contributors to the MYRRHA decay heat uncertainty. The calculated uncertainty values are deemed acceptable from the safety point of view as they are well within the available regulatory limits.

KW - Decay Heat

KW - uncertainty

KW - sensitivity

KW - depletion

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/26682603

U2 - 10.1051/epjconf/201714609021

DO - 10.1051/epjconf/201714609021

M3 - In-proceedings paper

VL - 146

T3 - EPJ Web of Conferences

SP - 1

EP - 4

BT - EPJ Web of Conferences

T2 - 2016 - ND

Y2 - 11 September 2016 through 16 September 2016

ER -

ID: 6775938