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Dive into the research topics where Diana Cuervo is active.

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Featured researches published by Diana Cuervo.


Science and Technology of Nuclear Installations | 2013

Assessment of CTF Boiling Transition and Critical Heat Flux Modeling Capabilities Using the OECD/NRC BFBT and PSBT Benchmark Databases

Maria N. Avramova; Diana Cuervo

Over the last few years, the Pennsylvania State University (PSU) under the sponsorship of the US Nuclear Regulatory Commission (NRC) has prepared, organized, conducted, and summarized two international benchmarks based on the NUPEC data—the OECD/NRC Full-Size Fine-Mesh Bundle Test (BFBT) Benchmark and the OECD/NRC PWR Sub-Channel and Bundle Test (PSBT) Benchmark. The benchmarks’ activities have been conducted in cooperation with the Nuclear Energy Agency/Organization for Economic Co-operation and Development (NEA/OECD) and the Japan Nuclear Energy Safety (JNES) Organization. This paper presents an application of the joint Penn State University/Technical University of Madrid (UPM) version of the well-known sub-channel code COBRA-TF (Coolant Boiling in Rod Array-Two Fluid), namely, CTF, to the steady state critical power and departure from nucleate boiling (DNB) exercises of the OECD/NRC BFBT and PSBT benchmarks. The goal is two-fold: firstly, to assess these models and to examine their strengths and weaknesses; and secondly, to identify the areas for improvement.


Science and Technology of Nuclear Installations | 2014

Selected Papers from OECD-NEA PSBT Benchmark

Maria N. Avramova; Annalisa Manera; D.R. Novog; Diana Cuervo; A. Petruzzi

Historically, the prediction of safety margins has been based on system level thermal-hydraulic calculations employing suitable empirical formulations for assembly specific geometries and fuel-element grid spacers. These works have assessed response, margins, and consequences for the system based on one-dimensional two-fluid or drift-flux type thermalhydraulics formulations with fuel-vendor specific hydraulic losses and heat transfer characteristics for various fuel assemblies, including the so-called hot channel. Analysis of the hot channel gives important information on flow rates, fuel element centerline temperature, fuel sheath temperature, and margin to the departure from nucleate boiling. Given the reliance of the above approaches on empirical formulations obtained from complex and often difficult experiments, there is significant interest in obtaining reliable and accurate results from computation tools which employ more fundamental empirical relationships which can be obtained from subsets of the domain or from other scaled experiments.


Annals of Nuclear Energy | 2006

Evaluation and enhancement of COBRA-TF efficiency for LWR calculations

Diana Cuervo; Maria N. Avramova; Kostadin Ivanov; Rafael Miró


Annals of Nuclear Energy | 2013

A comparative study of Monte Carlo-coupled depletion codes applied to a Sodium Fast Reactor design loaded with minor actinides

R. Ochoa; M. Vázquez; F. Álvarez-Velarde; F. Martín-Fuertes; N. García-Herranz; Diana Cuervo


Annals of Nuclear Energy | 2015

Boron dilution transient simulation analyses in a PWR with neutronics/thermal-hydraulics coupled codes in the NURISP project

Gonzalo Jimenez; José J. Herrero; A. Gommlich; S. Kliem; Diana Cuervo; J. Jimenez


Annals of Nuclear Energy | 2012

Neighborhood-corrected interface discontinuity factors for multi-group pin-by-pin diffusion calculations for LWR

José J. Herrero; N. García-Herranz; Diana Cuervo; Carol Ahnert


Archive | 2006

Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses

Maria N. Avramova; Diana Cuervo; Kostadin Ivanov


International Journal of Engineering Education | 2011

Education and Training of Future Nuclear Engineers Through the use of an Interactive Plant Simulator

Carol Ahnert; Diana Cuervo; N. García-Herranz; José-María Aragonés; O. Cabellos; Eduardo Gallego; Emilio Mínguez; A. Lorente; David Piedra; Luis Rebollo; Julio Blanco


Annals of Nuclear Energy | 2014

Effects of cross sections tables generation and optimization on rod ejection transient analyses

S. Sánchez-Cervera; N. García-Herranz; José J. Herrero; Diana Cuervo


Progress in Nuclear Energy | 2017

Impact of the homogenization level, nodal or pin-by-pin, on the uncertainty quantification with core simulators

E. Castro; S. Sánchez-Cervera; N. García-Herranz; Diana Cuervo

Collaboration


Dive into the Diana Cuervo's collaboration.

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N. García-Herranz

Technical University of Madrid

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Maria N. Avramova

Pennsylvania State University

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Carol Ahnert

Technical University of Madrid

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José J. Herrero

Technical University of Madrid

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S. Sánchez-Cervera

Technical University of Madrid

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Kostadin Ivanov

Pennsylvania State University

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A. Lorente

Technical University of Madrid

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David Piedra

Technical University of Madrid

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E. Castro

Technical University of Madrid

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Eduardo Gallego

Technical University of Madrid

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