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Šalamon L, Geslot B, Heyse J, Kopecky S, Leconte P, Noguere G, Paradela C, Schillebeeckx P, Snoj L. Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements. EPJ WEB OF CONFERENCES 2020. [DOI: 10.1051/epjconf/202023901022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
A characterisation of cylindrical samples by Neutron Resonance Transmission Analysis (NRTA) at the GELINA facility of JRC Geel (Belgium) is presented. The samples were designed and produced for reactivity worth measurements in the MINERVE reactor of CEA Cadarache (France). NRTA was applied to determine the nuclide composition of UO2, Al2O3 and liquid samples that were doped with silver. The volume number densities of 238U, 107Ag and 109Ag obtained by NRTA are within 2 % fully consistent with the values that are quoted by the manufacturer. In addition, the NRTA data reveal a tungsten contamination which is not reported by the provider. It is shown that such a contamination contributes by up to 5.7 % to the reactivity worth.
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Šalamon L, Geslot B, Heyse J, Kopecky S, Leconte P, Noguere G, Paradela C, Schillebeeckx P, Snoj L. Neutron resonance transmission analysis of cylindrical samples used for reactivity worth measurements. J Radioanal Nucl Chem 2019. [DOI: 10.1007/s10967-019-06611-9] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Rizzo A, Vaglio-Gaudard C, Noguere G, Eschbach R, Martin JF, Grassi G. Assessment of the 153Eu and 154Eu neutron capture cross sections from the integral data assimilation of used nuclear fuel experiments. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.09.035] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Rizzo A, Vaglio-Gaudard C, Noguere G, Eschbach R, Grassi G, Martin JF. Feedback from experimental isotopic compositions of used nuclear fuels on neutron cross sections and cumulative fission yields of the JEFF-3.1.1 library by using integral data assimilation. EPJ NUCLEAR SCIENCES & TECHNOLOGIES 2019. [DOI: 10.1051/epjn/2019056] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
Comparisons of calculated and experimental isotopic compositions of used nuclear fuels can provide valuable information on the quality of nuclear data involved in neutronic calculations. The experimental database used in the present study − containing more than a thousand isotopic ratio measurements for UOX and MOX fuels with burnup ranging from 10 GWd/t up to 85 GWd/t − allowed to investigate 45 isotopic ratios covering a large number of actinides (U, Np, Pu, Am and Cm) and fission products (Nd, Cs, Sm, Eu, Gd, Ru, Ce, Tc, Mo, Ag and Rh). The Integral Data Assimilation procedure implemented in the CONRAD code was used to provide nuclear data trends with realistic uncertainties for Pressurized Water Reactors (PWRs) applications. Results confirm the quality of the 235U, 239Pu and 241Pu neutron capture cross sections available in the JEFF-3.1.1 library; slight increases of +1.2 ± 2.4%, +0.5 ± 2.2% and +1.2 ± 4.2% are respectively suggested, these all being within the limits of the quoted uncertainties. Additional trends on the capture cross sections were also obtained for other actinides (236U, 238Pu, 240Pu, 242Pu, 241Am, 243Am, 245Cm) and fission products (103Rh, 153Eu, 154Eu) as well as for the 238U(n,2n) and 237Np(n,2n) reactions. Meaningful trends for the cumulative fission yields of 144Ce, 133Cs, 137Cs and 106Ru for the 235U(nth,f) and 239Pu(nth,f) reactions are also reported.
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Geslot B, Gruel A, Walczak P, Leconte P, Blaise P. A hybrid pile oscillator experiment in the Minerve reactor. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.04.036] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Leconte P, Vaglio-Gaudard C, Eschbach R, Antony M, Di-Salvo J, Pépino A. Reactivity Loss Validation of High-Burnup PWR Fuels with Pile-Oscillation Experiments in MINERVE. NUCL SCI ENG 2017. [DOI: 10.13182/nse12-56] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- P. Leconte
- CEA, DEN, DER0SPRC0LEPh, Cadarache, F-13108 St. Paul lez Durance
| | | | - R. Eschbach
- CEA, DEN, DER0SPRC0LECy, Cadarache, F-13108 St. Paul lez Durance
| | - M. Antony
- CEA, DEN, DER0SRJH, Cadarache, F-13108 St. Paul lez Durance
| | - J. Di-Salvo
- CEA, DEN, DER0SPEX0LPE, Cadarache, F-13108 St. Paul lez Durance
| | - A. Pépino
- CEA, DEN, DER0SPEX0LPE, Cadarache, F-13108 St. Paul lez Durance
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Leconte P, Geslot B, Gruel A, Pépino A. Thermal neutron activation experiments on Ag, In, Cs, Eu, V, Mo, Zn, Sn and Zr in the MINERVE facility. EPJ WEB OF CONFERENCES 2016. [DOI: 10.1051/epjconf/201611107001] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022] Open
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Chambon A, Santamarina A, Riffard C, Lavaud F, Lecarpentier D. Needs of reliable nuclear data and covariance matrices for Burnup Credit in JEFF-3 library. EPJ WEB OF CONFERENCES 2013. [DOI: 10.1051/epjconf/20134203001] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
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