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Hernandez Solis, Augusto
Publications (8 of 8) Show all publications
Rochman, D., Leray, O., Hursin, M., Ferroukhi, H., Vasiliev, A., Aures, A., . . . Fiorito, L. (2017). Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core. Nuclear Data Sheets, 139, 1-76
Open this publication in new window or tab >>Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core
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2017 (English)In: Nuclear Data Sheets, ISSN 0090-3752, E-ISSN 1095-9904, Vol. 139, p. 1-76Article in journal (Refereed) Published
Abstract [en]

Abstract The impact of the current nuclear data library covariances such as in ENDF/B-VII.1, JEFF-3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work. The uncertainties due to nuclear data are calculated for existing PWR and BWR fuel assemblies (with burn-up up to 40 GWd/tHM, followed by 10 years of cooling time) and for a simplified PWR full core model (without burn-up) for quantities such as k ∞ , macroscopic cross sections, pin power or isotope inventory. In this work, the method of propagation of uncertainties is based on random sampling of nuclear data, either from covariance files or directly from basic parameters. Additionally, possible biases on calculated quantities are investigated such as the self-shielding treatment. Different calculation schemes are used, based on CASMO, SCALE, DRAGON, MCNP or FISPACT-II, thus simulating real-life assignments for technical-support organizations. The outcome of such a study is a comparison of uncertainties with two consequences. One: although this study is not expected to lead to similar results between the involved calculation schemes, it provides an insight on what can happen when calculating uncertainties and allows to give some perspectives on the range of validity on these uncertainties. Two: it allows to dress a picture of the state of the knowledge as of today, using existing nuclear data library covariances and current methods.

National Category
Subatomic Physics
Identifiers
urn:nbn:se:uu:diva-316069 (URN)10.1016/j.nds.2017.01.001 (DOI)000393254900002 ()
Available from: 2017-02-24 Created: 2017-02-24 Last updated: 2017-11-29Bibliographically approved
Hernandez Solis, A., Sjöstrand, H. & Helgesson, P. (2017). Propagation of neutron-reaction uncertainties through multi-physics models of novel LWR's. In: Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S (Ed.), ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY: . Paper presented at ND 2016: International Conference on Nuclear Data for Science and Technology, SEP 11-16, 2016, Bruges, Belgium.. Les Ulis: EDP Sciences, 146, Article ID 02035.
Open this publication in new window or tab >>Propagation of neutron-reaction uncertainties through multi-physics models of novel LWR's
2017 (English)In: ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY / [ed] Plompen, A; Hambsch, FJ; Schillebeeckx, P; Mondelaers, W; Heyse, J; Kopecky, S; Siegler, P; Oberstedt, S, Les Ulis: EDP Sciences, 2017, Vol. 146, article id 02035Conference paper, Published paper (Refereed)
Abstract [en]

The novel design of the renewable boiling water reactor (RBWR) allows a breeding ratio greater than unity and thus, it aims at providing for a self-sustained fuel cycle. The neutron reactions that compose the different microscopic cross-sections and angular distributions are uncertain, so when they are employed in the determination of the spatial distribution of the neutron flux in a nuclear reactor, a methodology should be employed to account for these associated uncertainties. In this work, the Total Monte Carlo (TMC) method is used to propagate the different neutron-reactions (as well as angular distributions) covariances that are part of the TENDL-2014 nuclear data (ND) library. The main objective is to propagate them through coupled neutronic and thermal-hydraulic models in order to assess the uncertainty of important safety parameters related to multi-physics, such as peak cladding temperature along the axial direction of an RBWR fuel assembly. The objective of this study is to quantify the impact that ND covariances of important nuclides such as U-235, U-238, Pu-239 and the thermal scattering of hydrogen in H2O have in the deterministic safety analysis of novel nuclear reactors designs.

Place, publisher, year, edition, pages
Les Ulis: EDP Sciences, 2017
Series
EPJ Web of Conferences, ISSN 2100-014X
National Category
Subatomic Physics
Identifiers
urn:nbn:se:uu:diva-330372 (URN)10.1051/epjconf/201714602035 (DOI)000426429500051 ()978-2-7598-9020-0 (ISBN)
Conference
ND 2016: International Conference on Nuclear Data for Science and Technology, SEP 11-16, 2016, Bruges, Belgium.
Available from: 2017-09-28 Created: 2017-09-28 Last updated: 2018-06-29Bibliographically approved
Sjöstrand, H., Conroy, S., Helgesson, P., Hernandez Solis, A., Koning, A., Pomp, S. & Rochman, D. (2017). Propagation of nuclear data uncertainties for fusion power measurements. In: Plompen, A.; Hambsch, FJ.; Schillebeeckx, P.; Mondelaers, W.; Heyse, J.; Kopecky, S.; Siegler, P.; Oberstedt, S. (Ed.), ND 2016: International Conference On Nuclear Data For Science And Technology. Paper presented at ND 2016: International Conference On Nuclear Data For Science And Technology, Sep 11-16, 2016, Bruges, Belgium.. Les Ulis: EDP Sciences, 146(02034), Article ID 02034.
Open this publication in new window or tab >>Propagation of nuclear data uncertainties for fusion power measurements
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2017 (English)In: ND 2016: International Conference On Nuclear Data For Science And Technology / [ed] Plompen, A.; Hambsch, FJ.; Schillebeeckx, P.; Mondelaers, W.; Heyse, J.; Kopecky, S.; Siegler, P.; Oberstedt, S., Les Ulis: EDP Sciences, 2017, Vol. 146, no 02034, article id 02034Conference paper, Published paper (Refereed)
Abstract [en]

Neutron measurements using neutron activation systems are an essential part of the diagnostic system at large fusion machines such as JET and ITER. Nuclear data is used to infer the neutron yield. Consequently, high-quality nuclear data is essential for the proper determination of the neutron yield and fusion power. However, uncertainties due to nuclear data are not fully taken into account in uncertainty analysis for neutron yield calibrations using activation foils. This paper investigates the neutron yield uncertainty due to nuclear data using the so-called Total Monte Carlo Method. The work is performed using a detailed MCNP model of the JET fusion machine; the uncertainties due to the cross-sections and angular distributions in JET structural materials, as well as the activation cross-sections in the activation foils, are analysed. It is found that a significant contribution to the neutron yield uncertainty can come from uncertainties in the nuclear data.

Place, publisher, year, edition, pages
Les Ulis: EDP Sciences, 2017
Series
EPJ Web of Conferences, ISSN 2100-014X
National Category
Subatomic Physics
Identifiers
urn:nbn:se:uu:diva-343958 (URN)10.1051/epjconf/201714602034 (DOI)000426429500050 ()978-2-7598-9020-0 (ISBN)
Conference
ND 2016: International Conference On Nuclear Data For Science And Technology, Sep 11-16, 2016, Bruges, Belgium.
Available from: 2018-03-02 Created: 2018-03-02 Last updated: 2018-07-03Bibliographically approved
Hernandez Solis, A., Sjöstrand, H., Alhassan, E. & Helgesson, P. (2016). Development Of Drag-MOC: A tool for the study of uncertainty analysis through the deterministic OpenMOC transport code. In: : . Paper presented at Reactor physics meeting PHYSOR 2016.
Open this publication in new window or tab >>Development Of Drag-MOC: A tool for the study of uncertainty analysis through the deterministic OpenMOC transport code
2016 (English)Conference paper, Published paper (Refereed)
National Category
Engineering and Technology
Identifiers
urn:nbn:se:uu:diva-274321 (URN)
Conference
Reactor physics meeting PHYSOR 2016
Available from: 2016-01-20 Created: 2016-01-20 Last updated: 2017-02-06
Sjöstrand, H., Conroy, S., Helgesson, P., J. Koning, A., Hernandez Solis, A., Pomp, S. & Rochman, D. (2016). Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements. In: : . Paper presented at ND2016, International Conference on Nuclear Data for Science and Technology, 11-16/9 Bruges.
Open this publication in new window or tab >>Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements
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2016 (English)Conference paper, Oral presentation with published abstract (Refereed)
Abstract [en]

Fusion plasmas produce neutrons and by measuring the neutron emission the fusion power can be inferred. Accurate neutron yield measurements are paramount for the safe and efficient operation of fusion experiments and, eventually, fusion power plants.

Neutron measurements are an essential part of the diagnostic system at large fusion machines such as JET and ITER. At JET, a system of activation foils provides the absolute calibration for the neutron yield determination.  The activation system uses the property of certain nuclei to emit radiation after being excited by neutron reactions. A sample of suitable nuclei is placed in the neutron flux close to the plasma and after irradiation the induced radiation is measured.  Knowing the neutron activation cross section one can calculate the time-integrated neutron flux at the sample position. To relate the local flux to the total neutron yield, the spatial flux response has to be identified. This describes how the local neutron emission affects the flux at the detector.  The required spatial flux response is commonly determined using neutron transport codes, e.g., MCNP.

Nuclear data is used as input both in the calculation of the spatial flux response and when the flux at the irradiation site is inferred. Consequently, high quality nuclear data is essential for the proper determination of the neutron yield and fusion power.  However, uncertainties due to nuclear data are generally not fully taken into account in today’s uncertainty analysis for neutron yield calibrations using activation foils.  

In this paper, the neutron yield uncertainty due to nuclear data is investigated using the so-called Total Monte Carlo Method. The work is performed using a detailed MCNP model of JET fusion machine.  In this work the uncertainties due to the cross sections and angular distributions in JET structural materials, as well as the activation cross sections, are analyzed. It is shown that a significant contribution to the neutron yield uncertainty can come from uncertainties in the nuclear data.

National Category
Physical Sciences Fusion, Plasma and Space Physics Subatomic Physics
Research subject
Physics with specialization in Applied Nuclear Physics
Identifiers
urn:nbn:se:uu:diva-313491 (URN)
Conference
ND2016, International Conference on Nuclear Data for Science and Technology, 11-16/9 Bruges
Funder
EU, Horizon 2020
Available from: 2017-01-20 Created: 2017-01-20 Last updated: 2017-01-20Bibliographically approved
Hernandez Solis, A. (2015). Development of an in-house coupled neutronic and thermal-hydraulic code for the steady-state analysis of LWRs. In: : . Paper presented at 17th meeting on Reactor Physics in the Nordic Countries.
Open this publication in new window or tab >>Development of an in-house coupled neutronic and thermal-hydraulic code for the steady-state analysis of LWRs
2015 (English)Conference paper, Oral presentation only (Refereed)
National Category
Engineering and Technology
Identifiers
urn:nbn:se:uu:diva-274320 (URN)
Conference
17th meeting on Reactor Physics in the Nordic Countries
Available from: 2016-01-20 Created: 2016-01-20 Last updated: 2016-01-20
Hernandez Solis, A., Sjostrand, H., Alhassan, E. & Helgesson, P. (2015). DRAG-MOC: A tool for the study of uncertainty analysis through OpenMOC. In: : . Paper presented at WONDER 2015.
Open this publication in new window or tab >>DRAG-MOC: A tool for the study of uncertainty analysis through OpenMOC
2015 (English)Conference paper, Poster (with or without abstract) (Refereed)
National Category
Engineering and Technology
Identifiers
urn:nbn:se:uu:diva-274318 (URN)
Conference
WONDER 2015
Available from: 2016-01-20 Created: 2016-01-20 Last updated: 2017-01-30
Hernandez Solis, A. (2015). On the importance of the spatial dependence of gap properties in the design of modern fast reactor cores. In: : . Paper presented at 17th meeting on Reactor Physics in the Nordic Countries.
Open this publication in new window or tab >>On the importance of the spatial dependence of gap properties in the design of modern fast reactor cores
2015 (English)Conference paper, Oral presentation only (Refereed)
National Category
Engineering and Technology
Identifiers
urn:nbn:se:uu:diva-274319 (URN)
Conference
17th meeting on Reactor Physics in the Nordic Countries
Available from: 2016-01-20 Created: 2016-01-20 Last updated: 2016-01-20
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