Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor

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Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor. / Krása, Antonin; Kochetkov, Anatoly; Baeten, Peter; Vittiglio, Guido; Wagemans, Jan; Bécares, Vicente.

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

Research output: Contribution to report/book/conference proceedings › In-proceedings paper

Harvard

Krása, A, Kochetkov, A, Baeten, P, Vittiglio, G, Wagemans, J & Bécares, V 2017, Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor. in EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. 2017 edn, vol. 146, EPJ Web of Conferences, pp. 1-4. https://doi.org/10.1051/epjconf/201714606019

APA

Krása, A., Kochetkov, A., Baeten, P., Vittiglio, G., Wagemans, J., & Bécares, V. (2017). Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor. In EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology (2017 ed., Vol. 146, pp. 1-4). (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714606019

Vancouver

Krása A, Kochetkov A, Baeten P, Vittiglio G, Wagemans J, Bécares V. Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor. In EPJ Web of Conferences: ND 2016: International Conference on Nuclear Data for Science and Technology. 2017 ed. Vol. 146. 2017. p. 1-4. (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714606019

Author

Krása, Antonin ; Kochetkov, Anatoly ; Baeten, Peter ; Vittiglio, Guido ; Wagemans, Jan ; Bécares, Vicente. / Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor. 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{1cd19e3ded844bb5bb61d5256f8d9646,
title = "Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor",
abstract = "VENUS-F is a fast, zero-power reactor with 30{\%} wt. metallic uranium fuel and solid lead ascoolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented.",
keywords = "VENUS-F, MYRRHA, Monte Carlo, lead void, nuclear data library, fast neutron, MCNP, fuel Doppler, reactivity effects",
author = "Antonin Kr{\'a}sa and Anatoly Kochetkov and Peter Baeten and Guido Vittiglio and Jan Wagemans and Vicente B{\'e}cares",
note = "Score=3",
year = "2017",
month = "9",
day = "13",
doi = "10.1051/epjconf/201714606019",
language = "English",
volume = "146",
series = "EPJ Web of Conferences",
publisher = "EDP Sciences",
pages = "1--4",
booktitle = "EPJ Web of Conferences",
edition = "2017",

}

RIS - Download

TY - GEN

T1 - Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor

AU - Krása, Antonin

AU - Kochetkov, Anatoly

AU - Baeten, Peter

AU - Vittiglio, Guido

AU - Wagemans, Jan

AU - Bécares, Vicente

N1 - Score=3

PY - 2017/9/13

Y1 - 2017/9/13

N2 - VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead ascoolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented.

AB - VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead ascoolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented.

KW - VENUS-F

KW - MYRRHA

KW - Monte Carlo

KW - lead void

KW - nuclear data library

KW - fast neutron

KW - MCNP

KW - fuel Doppler

KW - reactivity effects

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/31508971

U2 - 10.1051/epjconf/201714606019

DO - 10.1051/epjconf/201714606019

M3 - In-proceedings paper

VL - 146

T3 - EPJ Web of Conferences

SP - 1

EP - 4

BT - EPJ Web of Conferences

ER -

ID: 6776099