Revision of Fission Yields Uncertainties in ENDF/B-VIII.0

The measurement of radioactive fission products from nuclear events has important implications for nuclear data production, environmental monitoring, and nuclear forensics. In a previous paper, the authors reported the optimization of an intra-group lanthanide separation using LN extraction resin from Eichrom Technologies®, Inc. and a nitric acid gradient. In this work, the method was demonstrated for the separation and quantification of multiple short-lived fission product lanthanide isotopes from a fission product sample produced from the thermal irradiation of highly enriched uranium. The separations were performed in parallel in quadruplicate with reproducible results and high decontamination factors for 153Sm, 156Eu, and 161Tb. Based on the results obtained here, the fission yields for 144Ce, 153Sm, 156Eu, and 161Tb are consistent with published fission yields. This work demonstrates the effectiveness of the separations for the intended application of short-lived lanthanide fission product analysis requiring high decontamination factors.

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From fission yield measurements to evaluation: status on statistical methodology for the covariance question

EPJ Nuclear Sciences & Technologies ◽

10.1051/epjn/2018030 ◽

2018 ◽

Vol 4 ◽

pp. 26 ◽

Cited By ~ 1

Author(s):

Brieuc Voirin ◽

Grégoire Kessedjian ◽

Abdelaziz Chebboubi ◽

Sylvain Julien-Laferrière ◽

Olivier Serot

Keyword(s):

Statistical Tests ◽

Fission Products ◽

Experimental Program ◽

Mass Yield ◽

Statistical Methodology ◽

Fission Yield ◽

Fission Process ◽

Induced Fission ◽

Entropy Criterion ◽

Fission Yields

Studies on fission yields have a major impact on the characterization and the understanding of the fission process and are mandatory for reactor applications. Fission yield evaluation represents the synthesis of experimental and theoretical knowledge to perform the best estimation of mass, isotopic and isomeric yields. Today, the output of fission yield evaluation is available as a function of isotopic yields. Without the explicitness of evaluation covariance data, mass yield uncertainties are greater than those of isotopic yields. This is in contradiction with experimental knowledge where the abundance of mass yield measurements is dominant. These last years, different covariance matrices have been suggested but the experimental part of those are neglected. The collaboration between the LPSC Grenoble and the CEA Cadarache starts a new program in the field of the evaluation of fission products in addition to the current experimental program at Institut Laue-Langevin. The goal is to define a new methodology of evaluation based on statistical tests to define the different experimental sets in agreement, giving different solutions for different analysis choices. This study deals with the thermal neutron induced fission of 235U. The mix of data is non-unique and this topic will be discussed using the Shannon entropy criterion in the framework of the statistical methodology proposed.

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Extensive Study of the Quality of Fission Yields from Experiment, Evaluation and GEF for Antineutrino Studies and Applications

Nuclear Data Sheets ◽

10.1016/j.nds.2021.04.004 ◽

2021 ◽

Vol 173 ◽

pp. 54-117

Author(s):

K.-H. Schmidt ◽

M. Estienne ◽

M. Fallot ◽

S. Cormon ◽

A. Cucoanes ◽

...

Keyword(s):

Extensive Study ◽

Fission Yields

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Cumulative yields of stable and long-lived isotopes of tin in neutron-induced fission

Canadian Journal of Physics ◽

10.1139/p83-193 ◽

1983 ◽

Vol 61 (11) ◽

pp. 1490-1497 ◽

Cited By ~ 5

Author(s):

K. J. R. Rosman ◽

J. R. De Laeter ◽

J. W. Boldeman ◽

H. G. Thode

Keyword(s):

Stable Isotopes ◽

Fine Structure ◽

Fission Product ◽

Mass Spectrometer ◽

Smooth Curve ◽

Mass Region ◽

Neutron Fission ◽

Source Mass ◽

Induced Fission ◽

Fission Yields

The relative cumulative fission yields of the six stable isotopes of tin (117Sn,118Sn, 119Sn, 120Sn, 122Sn, and 124Sn) and the long-lived isotope 126Sn have been measured in the thermal and epicadium neutron fission of 233U and 235U, and the epicadium neutron fission of 238U. Nanogram-sized fission product tin samples were extracted from irradiated uranium samples and analyzed in a solid source mass spectrometer. In each case a smooth curve can be drawn through the yield points of the seven isotopes of tin. There is, therefore, no evidence of "fine structure" in the 117 ≤ A ≤ 126 portion of the symmetric mass region.

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Journal of Radioanalytical and Nuclear Chemistry ◽

10.1007/s10967-005-0701-1 ◽

2005 ◽

Vol 264 (1) ◽

pp. 243-253 ◽

Cited By ~ 2

Author(s):

E. L. Reber ◽

R. J. Gehrke ◽

R. Aryaeinejad ◽

R. J. K. Hartwell

Keyword(s):

Fission Product ◽

Gamma Rays ◽

Fission Yields

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Cross Section and Fission Yields Induced Uncertainty in the Vver-440 Burnup Calculation

Journal of Nuclear Engineering and Radiation Science ◽

10.1115/1.4051613 ◽

2021 ◽

Author(s):

Branislav Vrban ◽

Stefan Cerba ◽

Jakub Luley ◽

Filip Osuský ◽

Vladimir Necas

Keyword(s):

Cross Section ◽

Neutron Cross Section ◽

Nuclear Data ◽

Reactor Operation ◽

Precise Estimation ◽

Stochastic Techniques ◽

Core Characteristics ◽

Fission Yields ◽

Operational Data ◽

Burnup Calculation

Abstract The properties of nuclear fuel depend on the actual isotopic composition which develops during a reactor operation. In practice, the prediction accuracy of burnup calculations serves as the basis for the future precise estimation of a core lifetime and other safety-based core characteristics. The present study quantifies nuclear data induced uncertainties of nuclide concentrations and multiplication factors in VVER-440 fuel depletion analysis. The well-known SCALE system and the TRITON sequence are used with the NEWT deterministic solver in the SAMPLER module that implements stochastic techniques to assess the uncertainty in computed results. The propagation of uncertainties in neutron cross section and fission yields is studied through the depletion calculation of 2D heterogeneous VVER-440 fuel assembly with an average enrichment of 4.87 wt % of 235U and six gadolinium rods with 3.35 % of Gd2O3. In the paper, fixed nominal depletion conditions are based on the real operational data of the Slovak NPP Bohunice unit 4 during cycle 30. In total 250 cases with uncertain parameters are computed and the results are evaluated by an auxiliary tool.

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