Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores

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Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores. / Kochetkov, Anatoly; Krása, Antonin; Baeten, Peter; Vittiglio, Guido; Wagemans, Jan; Bécares, Vicente; Bianchini, Giancarlo; Valentina, Fabrizio; Carta, Mario; Firpo, Gabriele; Fridman, Emil; Sarotto, Massimo.

EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. Vol. 146 2017. ed. 2017. p. 1-4 06007 (EPJ Web of Conferences).

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

Harvard

Kochetkov, A, Krása, A, Baeten, P, Vittiglio, G, Wagemans, J, Bécares, V, Bianchini, G, Valentina, F, Carta, M, Firpo, G, Fridman, E & Sarotto, M 2017, Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores. in EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. 2017 edn, vol. 146, 06007, EPJ Web of Conferences, pp. 1-4, 2016 - ND, Bruges, Belgium, 2016-09-11. https://doi.org/10.1051/epjconf/201714606007

APA

Kochetkov, A., Krása, A., Baeten, P., Vittiglio, G., Wagemans, J., Bécares, V., ... Sarotto, M. (2017). Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores. In EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology (2017 ed., Vol. 146, pp. 1-4). [06007] (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714606007

Vancouver

Kochetkov A, Krása A, Baeten P, Vittiglio G, Wagemans J, Bécares V et al. Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores. In EPJ Web of Conferences: ND 2016: International conference on nuclear data for science and technology. 2017 ed. Vol. 146. 2017. p. 1-4. 06007. (EPJ Web of Conferences). https://doi.org/10.1051/epjconf/201714606007

Author

Kochetkov, Anatoly ; Krása, Antonin ; Baeten, Peter ; Vittiglio, Guido ; Wagemans, Jan ; Bécares, Vicente ; Bianchini, Giancarlo ; Valentina, Fabrizio ; Carta, Mario ; Firpo, Gabriele ; Fridman, Emil ; Sarotto, Massimo. / Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores. 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{038b1730625e46368f2b9b0b8c36febd,
title = "Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores",
abstract = "During the GUINEVERE FP6 European project (2006–2011), the zero-power VENUS water moderated reactor was modified into VENUS-F, a mock-up of a lead cooled fast spectrum system with solid components that can be operated in both critical and subcritical mode. The Fast Reactor Experiments for hybrid Applications (FREYA) FP7 project was launched in 2011 to support the designs of the MYRRHA Accelerator Driven System (ADS) and the ALFRED Lead Fast Reactor (LFR). Three VENUS-F critical core configurations, simulating the complex MYRRHA core design and one configuration devoted to the LFR ALFRED core conditions were investigated in 2015. The MYRRHA related cores simulated step by step design peculiarities like the BeO reflector and in pile sections. For all of these cores the fuel assemblies were of a simple design consisting of 30{\%} enriched metallic uranium, lead rodlets to simulate the coolant and Al2O3 rodlets to simulate the oxide fuel. Fission rate ratios of minor actinides such as Np-237, Am-241 as well as Pu-239, Pu-240, Pu-242 and U-238 to U-235 were measured in these VENUS-F critical assemblies with small fission chambers in specially designed locations, to determine the spectral indices in the different neutron spectrum conditions. The measurements have been analyzed using advanced computational tools including deterministic and stochastic codes and different nuclear data sets like JEFF-3.1, JEFF-3.2, ENDF/B7.1 and JENDL-4.0. The analysis of the C/E discrepancies will help to improve the nuclear data in the specific energy region of fast neutron reactor spectra.",
keywords = "VENUS-F, MYRRHA, spectrum index, fast reactor, ALFRED",
author = "Anatoly Kochetkov and Antonin Kr{\'a}sa and Peter Baeten and Guido Vittiglio and Jan Wagemans and Vicente B{\'e}cares and Giancarlo Bianchini and Fabrizio Valentina and Mario Carta and Gabriele Firpo and Emil Fridman and Massimo Sarotto",
note = "Score=3",
year = "2017",
month = "9",
day = "13",
doi = "10.1051/epjconf/201714606007",
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 - Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores

AU - Kochetkov, Anatoly

AU - Krása, Antonin

AU - Baeten, Peter

AU - Vittiglio, Guido

AU - Wagemans, Jan

AU - Bécares, Vicente

AU - Bianchini, Giancarlo

AU - Valentina, Fabrizio

AU - Carta, Mario

AU - Firpo, Gabriele

AU - Fridman, Emil

AU - Sarotto, Massimo

N1 - Score=3

PY - 2017/9/13

Y1 - 2017/9/13

N2 - During the GUINEVERE FP6 European project (2006–2011), the zero-power VENUS water moderated reactor was modified into VENUS-F, a mock-up of a lead cooled fast spectrum system with solid components that can be operated in both critical and subcritical mode. The Fast Reactor Experiments for hybrid Applications (FREYA) FP7 project was launched in 2011 to support the designs of the MYRRHA Accelerator Driven System (ADS) and the ALFRED Lead Fast Reactor (LFR). Three VENUS-F critical core configurations, simulating the complex MYRRHA core design and one configuration devoted to the LFR ALFRED core conditions were investigated in 2015. The MYRRHA related cores simulated step by step design peculiarities like the BeO reflector and in pile sections. For all of these cores the fuel assemblies were of a simple design consisting of 30% enriched metallic uranium, lead rodlets to simulate the coolant and Al2O3 rodlets to simulate the oxide fuel. Fission rate ratios of minor actinides such as Np-237, Am-241 as well as Pu-239, Pu-240, Pu-242 and U-238 to U-235 were measured in these VENUS-F critical assemblies with small fission chambers in specially designed locations, to determine the spectral indices in the different neutron spectrum conditions. The measurements have been analyzed using advanced computational tools including deterministic and stochastic codes and different nuclear data sets like JEFF-3.1, JEFF-3.2, ENDF/B7.1 and JENDL-4.0. The analysis of the C/E discrepancies will help to improve the nuclear data in the specific energy region of fast neutron reactor spectra.

AB - During the GUINEVERE FP6 European project (2006–2011), the zero-power VENUS water moderated reactor was modified into VENUS-F, a mock-up of a lead cooled fast spectrum system with solid components that can be operated in both critical and subcritical mode. The Fast Reactor Experiments for hybrid Applications (FREYA) FP7 project was launched in 2011 to support the designs of the MYRRHA Accelerator Driven System (ADS) and the ALFRED Lead Fast Reactor (LFR). Three VENUS-F critical core configurations, simulating the complex MYRRHA core design and one configuration devoted to the LFR ALFRED core conditions were investigated in 2015. The MYRRHA related cores simulated step by step design peculiarities like the BeO reflector and in pile sections. For all of these cores the fuel assemblies were of a simple design consisting of 30% enriched metallic uranium, lead rodlets to simulate the coolant and Al2O3 rodlets to simulate the oxide fuel. Fission rate ratios of minor actinides such as Np-237, Am-241 as well as Pu-239, Pu-240, Pu-242 and U-238 to U-235 were measured in these VENUS-F critical assemblies with small fission chambers in specially designed locations, to determine the spectral indices in the different neutron spectrum conditions. The measurements have been analyzed using advanced computational tools including deterministic and stochastic codes and different nuclear data sets like JEFF-3.1, JEFF-3.2, ENDF/B7.1 and JENDL-4.0. The analysis of the C/E discrepancies will help to improve the nuclear data in the specific energy region of fast neutron reactor spectra.

KW - VENUS-F

KW - MYRRHA

KW - spectrum index

KW - fast reactor

KW - ALFRED

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/31464779

U2 - 10.1051/epjconf/201714606007

DO - 10.1051/epjconf/201714606007

M3 - In-proceedings paper

VL - 146

T3 - EPJ Web of Conferences

SP - 1

EP - 4

BT - EPJ Web of Conferences

ER -

ID: 6776036