Neutron-induced nuclear data for the MYRRHA fast spectrum facility

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Neutron-induced nuclear data for the MYRRHA fast spectrum facility. / Romojaro, P.; Zerovnik, G.; Alvarez-Velarde, F.; Stankovskiy, Alexey; Kodeli, I.; Fiorito, Luca; Diez, C.J.; Cabellos, O.; Garcia-Herranz, N.; Heyse, J.; Paradela, C.; Schillebeeckx, P.; Van den Eynde, Gert.

EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. Vol. 146 2017. p. 1-4 09007 (EPJ Web of Conferences).

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

Harvard

Romojaro, P, Zerovnik, G, Alvarez-Velarde, F, Stankovskiy, A, Kodeli, I, Fiorito, L, Diez, CJ, Cabellos, O, Garcia-Herranz, N, Heyse, J, Paradela, C, Schillebeeckx, P & Van den Eynde, G 2017, Neutron-induced nuclear data for the MYRRHA fast spectrum facility. in EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. vol. 146, 09007, EPJ Web of Conferences, pp. 1-4, 2016 - ND, Bruges, Belgium, 2016-09-11. https://doi.org/10.1051/epjconf/201714609007

APA

Romojaro, P., Zerovnik, G., Alvarez-Velarde, F., Stankovskiy, A., Kodeli, I., Fiorito, L., Diez, C. J., Cabellos, O., Garcia-Herranz, N., Heyse, J., Paradela, C., Schillebeeckx, P., & Van den Eynde, G. (2017). Neutron-induced nuclear data for the MYRRHA fast spectrum facility. In EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology (Vol. 146, pp. 1-4). [09007] (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714609007

Vancouver

Romojaro P, Zerovnik G, Alvarez-Velarde F, Stankovskiy A, Kodeli I, Fiorito L et al. Neutron-induced nuclear data for the MYRRHA fast spectrum facility. In EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. Vol. 146. 2017. p. 1-4. 09007. (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714609007

Author

Romojaro, P. ; Zerovnik, G. ; Alvarez-Velarde, F. ; Stankovskiy, Alexey ; Kodeli, I. ; Fiorito, Luca ; Diez, C.J. ; Cabellos, O. ; Garcia-Herranz, N. ; Heyse, J. ; Paradela, C. ; Schillebeeckx, P. ; Van den Eynde, Gert. / Neutron-induced nuclear data for the MYRRHA fast spectrum facility. EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. Vol. 146 2017. pp. 1-4 (EPJ Web of Conferences).

Bibtex - Download

@inproceedings{c31fb0c402664f7698fc4ed82e450049,
title = "Neutron-induced nuclear data for the MYRRHA fast spectrum facility",
abstract = "The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta)Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.",
keywords = "fast spectrum, uncertainty, sensitivity, lead, bismuth",
author = "P. Romojaro and G. Zerovnik and F. Alvarez-Velarde and Alexey Stankovskiy and I. Kodeli and Luca Fiorito and C.J. Diez and O. Cabellos and N. Garcia-Herranz and J. Heyse and C. Paradela and P. Schillebeeckx 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/201714609007",
language = "English",
volume = "146",
series = "EPJ Web of Conferences",
publisher = "EDP Sciences",
pages = "1--4",
booktitle = "EPJ Web of Conferences",
url = "http://www.nd2016.eu/",

}

RIS - Download

TY - GEN

T1 - Neutron-induced nuclear data for the MYRRHA fast spectrum facility

AU - Romojaro, P.

AU - Zerovnik, G.

AU - Alvarez-Velarde, F.

AU - Stankovskiy, Alexey

AU - Kodeli, I.

AU - Fiorito, Luca

AU - Diez, C.J.

AU - Cabellos, O.

AU - Garcia-Herranz, N.

AU - Heyse, J.

AU - Paradela, C.

AU - Schillebeeckx, P.

AU - Van den Eynde, Gert

N1 - Score=3

PY - 2017/9/18

Y1 - 2017/9/18

N2 - The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta)Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.

AB - The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta)Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.

KW - fast spectrum

KW - uncertainty

KW - sensitivity

KW - lead

KW - bismuth

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/26685733

U2 - 10.1051/epjconf/201714609007

DO - 10.1051/epjconf/201714609007

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: 6776156