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Volume 205

Number 12

Table of Contents
Foreword: Selected papers from the 2018 Best Estimate Plus Uncertainty International Conference (BEPU 2018)(Alessandro Petruzzi, Kostadin Ivanov, Evgeny Ivanov)
Technical Reviewers, 2019

Challenges in Application of BEPU for Risk Evaluations

Dumitru Serghiuta, John Tholammakkil

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1513-1528

Critical Review / dx.doi.org/10.1080/00295450.2019.1570751

Best Estimate Plus Uncertainty (BEPU): Why It Is Still Not Widely Used

Evgeny Ivanov, Giovanni Bruna, Antonio Sargeni, Franck Dubois

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1529-1539

Technical Paper / dx.doi.org/10.1080/00295450.2019.1627122

Verification and Validation and Uncertainty Quantification of Code Models

Tomasz Skorek

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1540-1553

Technical Paper / dx.doi.org/10.1080/00295450.2019.1580532

The CASUALIDAD Method for Uncertainty Evaluation of Best-Estimate System Thermal-Hydraulic Calculations

A. Petruzzi

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1554-1566

Technical Paper / dx.doi.org/10.1080/00295450.2019.1632092

RIPS, a Statistical Method for Characterizing the Limiting Scenario in a BEPU Approach

Jean-Christophe Lecoy, Jean-Yves Sauvage, Camille Charignon

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1567-1577

Technical Paper / dx.doi.org/10.1080/00295450.2019.1580528

Applications of Multivariate Normal Bayesian Models in Nuclear Engineering

Axel Hoefer, Oliver Buss, Michael Schmid

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1578-1587

Technical Paper / dx.doi.org/10.1080/00295450.2018.1560784

Advanced Methodology for Uncertainty Propagation in Computer Experiments with Large Number of Inputs

Bertrand Iooss, Amandine Marrel

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1588-1606

Technical Paper / dx.doi.org/10.1080/00295450.2019.1573617

Quantified Validation with Uncertainty Analysis for Turbulent Single-Phase Friction Models

Nathan W. Porter, Vincent A. Mousseau, Maria N. Avramova

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1607-1617

Technical Paper / dx.doi.org/10.1080/00295450.2018.1548221

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core

Kaiyue Zeng, Jason Hou, Kostadin Ivanov, Matthew Anderson Jessee

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1618-1637

Technical Paper / dx.doi.org/10.1080/00295450.2019.1580533

Global Sensitivity and Registration Strategy for Temperature Profile of Reflood Experiment Simulations

Grégory Perret, Damar Wicaksono, Ivor D. Clifford, Hakim Ferroukhi

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1638-1651

Technical Paper / dx.doi.org/10.1080/00295450.2019.1591154

Proposal of a Statistical Evaluation Method for the Criticality of the Fukushima Daiichi Nuclear Power Plants

Yuichi Morimoto, Masanori Akaike, Satoshi Takeo, Hiromi Maruyama

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1652-1660

Technical Paper / dx.doi.org/10.1080/00295450.2019.1580529

BEPU Method Applied to CFD Simulation of Mixing Flows

Andrej Prošek, Boštjan Končar, Matjaž Leskovar

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1661-1674

Technical Paper / dx.doi.org/10.1080/00295450.2018.1562820

Cross-Section Generation Using TXT2NTAB Code for Uncertainty Propagation with Burnup Dependence

A. Labarile, C. Mesado, R. Miró, G. Verdú

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1675-1684

Technical Paper / dx.doi.org/10.1080/00295450.2019.1631051

A Mutual Information–Based Experimental Design Framework to Use High-Fidelity Nuclear Reactor Codes to Calibrate Low-Fidelity Codes

Natalie Gordon, Lindsay Gilkey, Ralph C. Smith, Isaac Michaud, Brian Williams, Vincent Mousseau, Russell Hooper, Chris Jones

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1685-1696

Technical Paper / dx.doi.org/10.1080/00295450.2019.1590073

Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF

Robert K. Salko, William D. Pointer, Marc-Oliver Delchini, William L. Gurecky, Kevin T. Clarno, Stuart R. Salttery, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 205 / Number 12 / December 2019 / Pages 1697-1706

Technical Paper / dx.doi.org/10.1080/00295450.2019.1585734