Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores
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 App...
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doaj-694779df7c8d474380bedef00f16afee2021-08-02T01:05:28ZengEDP SciencesEPJ Web of Conferences2100-014X2017-01-011460600710.1051/epjconf/201714606007epjconf-nd2016_06007Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F coresKochetkov Anatoly0Krása Antonín1Baeten Peter2Vittiglio Guido3Wagemans Jan4Bécares Vicente5Bianchini Giancarlo6Fabrizio Valentina7Carta Mario8Firpo Gabriele9Fridman Emil10Sarotto Massimo11Belgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems InstituteBelgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems InstituteBelgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems InstituteBelgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems InstituteBelgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems InstituteCIEMATENEA CASACCIA, Energy and Sustainable Economic DevelopmentENEA CASACCIA, Energy and Sustainable Economic DevelopmentENEA CASACCIA, Energy and Sustainable Economic DevelopmentANSALDO NUCLEARE, S.p.AHZDRENEA UTFISSM-PRONOC, Energy and Sustainable Economic DevelopmentDuring 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.https://doi.org/10.1051/epjconf/201714606007 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Kochetkov Anatoly Krása Antonín Baeten Peter Vittiglio Guido Wagemans Jan Bécares Vicente Bianchini Giancarlo Fabrizio Valentina Carta Mario Firpo Gabriele Fridman Emil Sarotto Massimo |
spellingShingle |
Kochetkov Anatoly Krása Antonín Baeten Peter Vittiglio Guido Wagemans Jan Bécares Vicente Bianchini Giancarlo Fabrizio Valentina 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 |
author_facet |
Kochetkov Anatoly Krása Antonín Baeten Peter Vittiglio Guido Wagemans Jan Bécares Vicente Bianchini Giancarlo Fabrizio Valentina Carta Mario Firpo Gabriele Fridman Emil Sarotto Massimo |
author_sort |
Kochetkov Anatoly |
title |
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores |
title_short |
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores |
title_full |
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores |
title_fullStr |
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores |
title_full_unstemmed |
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores |
title_sort |
analysis of c/e results of fission rate ratio measurements in several fast lead venus-f cores |
publisher |
EDP Sciences |
series |
EPJ Web of Conferences |
issn |
2100-014X |
publishDate |
2017-01-01 |
description |
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. |
url |
https://doi.org/10.1051/epjconf/201714606007 |
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