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Propagation of Nuclear Data Uncertainties in Transmutation Calculations Using ACAB Code
O. Cabellos,N. Garcia-Herranz,Carlos J. Diez de la Obra,R. Alvarez-Cascos,J. Sanz,F. Ogando,P. Sauvan 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
The assessment of the accuracy of parameters related to the reactor core performance (e.g. keff) and fuel cycle (e.g. isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) can be used to address by computational simulation the systematic propagation of uncertainties on the final parameters. To perform this uncertainty assessment, the ENDF covariance files (variance/correlation in energy and cross-reactions-isotopes correlations) are required.In this paper, we assess the impact of ND uncertainties on the isotopic prediction for a conceptual design of a modular European Facility for Industrial Transmutation (EFIT) for a discharge burnup of 150 GWd/tHM. The complete set of uncertainty data for cross sections (EAF2007/UN, SCALE6.0/COVA-44G), radioactive decay and fission yield data (JEFF-3.1.1) are processed and used in ACAB code.
Propagation of Nuclear Data Uncertainties for PWR Core Analysis
O. CABELLOS,E. CASTRO,C. AHNERT,C. HOLGADO 한국원자력학회 2014 Nuclear Engineering and Technology Vol.46 No.3
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear design analysis toassess the impact of nuclear data uncertainties. The importance of the nuclear data uncertainties for 235,238U, 239Pu, and thethermal scattering library for hydrogen in water is analyzed. This uncertainty analysis is compared with the design andacceptance criteria to assure the adequacy of bounding estimates in safety margins.
PROPAGATION OF NUCLEAR DATA UNCERTAINTIES FOR PWR CORE ANALYSIS
Cabellos, O.,Castro, E.,Ahnert, C.,Holgado, C. Korean Nuclear Society 2014 Nuclear Engineering and Technology Vol.46 No.3
An uncertainty propagation methodology based on the Monte Carlo method is applied to PWR nuclear design analysis to assess the impact of nuclear data uncertainties. The importance of the nuclear data uncertainties for $^{235,238}U$, $^{239}Pu$, and the thermal scattering library for hydrogen in water is analyzed. This uncertainty analysis is compared with the design and acceptance criteria to assure the adequacy of bounding estimates in safety margins.
Finding largest rectangles in convex polygons
Cabello, S.,Cheong, O.,Knauer, C.,Schlipf, L. Elsevier 2016 Computational Geometry Vol.51 No.-
<P>We consider the following geometric optimization problem: find a maximum-area rectangle and a maximum-perimeter rectangle contained in a given convex polygon with n vertices. We give exact algorithms that solve these problems in time O(n(3)). We also give (1 - epsilon)-approximation algorithms that take time O(epsilon(-1/2) log n + epsilon(-3/2)). (C) 2015 Elsevier B.V. All rights reserved.</P>