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Featured researches published by J.S. Martínez.


Nuclear Engineering and Technology | 2014

NUCLEAR DATA UNCERTAINTY AND SENSITIVITY ANALYSIS WITH XSUSA FOR FUEL ASSEMBLY DEPLETION CALCULATIONS

W. Zwermann; A. Aures; L. Gallner; V. Hannstein; B. Krzykacz-Hausmann; K. Velkov; J.S. Martínez

Uncertainty and sensitivity analyses with respect to nuclear data are performed with depletion calculations for BWR and PWR fuel assemblies specified in the framework of the UAM-LWR Benchmark Phase II. For this, the GRS sampling based tool XSUSA is employed together with the TRITON depletion sequences from the SCALE 6.1 code system. Uncertainties for multiplication factors and nuclide inventories are determined, as well as the main contributors to these result uncertainties by calculating importance indicators. The corresponding neutron transport calculations are performed with the deterministic discrete-ordinates code NEWT. In addition, the Monte Carlo code KENO in multi-group mode is used to demonstrate a method with which the number of neutron histories per calculation run can be substantially reduced as compared to that in a calculation for the nominal case without uncertainties, while uncertainties and sensitivities are obtained with almost the same accuracy.


Annals of Nuclear Energy | 2013

Monte Carlo uncertainty propagation approaches in ADS burn-up calculations

C.J. Díez; O. Cabellos; D. Rochman; A. J. Koning; J.S. Martínez


Nuclear Data Sheets | 2014

Propagation of Neutron Cross Section, Fission Yield, and Decay Data Uncertainties in Depletion Calculations

J.S. Martínez; W. Zwermann; L. Gallner; F. Puente-Espel; O. Cabellos; K. Velkov; V. Hannstein


Nuclear Data Sheets | 2014

Impact of Nuclear Data Uncertainties on Advanced Fuel Cycles and their Irradiated Fuel – a Comparison between Libraries

C.J. Díez; O. Cabellos; J.S. Martínez


Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011) | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2011 | 08/05/2011 - 12/05/2011 | Río de Janeiro, Brasil | 2011

PROPAGATION OF NUCLEAR DATA UNCERTAINTIES IN FUEL CYCLE CALCULATIONS USING MONTE-CARLO TECHNIQUE

Oscar Luis Cabellos de Francisco; Carlos Javier Diez de la Obra; J.S. Martínez


Nuclear Data Sheets | 2014

Testing JEFF-3.1.1 and ENDF/B-VII.1 Decay and Fission Yield Nuclear Data Libraries with Fission Pulse Neutron Emission and Decay Heat Experiments

O. Cabellos; V. de Fusco; C.J. Diez de la Obra; J.S. Martínez; E. Gonzalez; D. Cano-Ott; F. Alvarez-Velarde


Nuclear Data Sheets | 2014

Analysis of 238Pu and 56Fe Evaluated Data for Use in MYRRHA

C.J. Díez; O. Cabellos; J.S. Martínez; A. Stankovskiy; G. Van den Eynde; P. Schillebeeckx; J. Heyse


Annals of Nuclear Energy | 2013

Methodologies for an improved prediction of the isotopic content in high burnup samples. Application to Vandellós-II reactor core

J.S. Martínez; O. Cabellos; C.J. Díez


EPJ Web of Conferences, ISSN 2100-014X, 2012-05, Vol. 27, No. 4 | 2012

Importance of Nuclear Data Uncertainties in Criticality Calculations

C. Ceresio; O. Cabellos; J.S. Martínez; C.J. Díez


Transactions of the american nuclear society | 2011

Impact of Nuclear Data Uncertainties in the Phase-1B Benchmark

Oscar Luis Cabellos de Francisco; J.S. Martínez; Carlos Javier Diez de la Obra

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O. Cabellos

Technical University of Madrid

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C.J. Díez

Technical University of Madrid

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C. Ceresio

Technical University of Madrid

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C.J. Diez de la Obra

Technical University of Madrid

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Diana Cuervo Gómez

Technical University of Madrid

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V. de Fusco

Technical University of Madrid

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D. Rochman

Nuclear Research and Consultancy Group

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A. J. Koning

International Atomic Energy Agency

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