Science and Technology of Nuclear Installations

Uncertainty Analysis in Reactor Physics Modeling


Publishing date
02 Nov 2012
Status
Published
Submission deadline
15 Jun 2012

Lead Editor

1Pennsylvania State University, University Park, PA, USA

2ENEA, Rome, Italy

3Department of Nuclear Engineering, Universidad Politecnica de Madrid, Madrid, Spain


Uncertainty Analysis in Reactor Physics Modeling

Description

OECD/NEA has initiated an international Uncertainty Analysis in Modeling (UAM) benchmark focused on uncertainties in modeling of Light Water Reactor (LWR) steady states and transients. The objective is to benchmark uncertainty and sensitivity analysis methods in coupled multiphysics and multiscale LWR calculations. The general frame of the OECD LWR UAM benchmark consists of three phases. The focus of this call for papers is Phase I (Neutronics Phase)—stand-alone reactor physics calculations—consisting of three exercises:

  • Exercise I-1: “Cell Physics”—derivation of the multigroup microscopic cross-section libraries and associated uncertainties.
  • Exercise I-2: “Lattice Physics”—derivation of the few-group macroscopic cross-section libraries and associated uncertainties.
  • Exercise I-3: “Core Physics”—core steady state stand-alone neutronics calculations and associated uncertainties.

We invite authors to submit original research and review articles related to the advances in the uncertainty and sensitivity analysis related to reactor physics modeling. The benchmark participants in UAM Phase I are invited to submit their papers based on their work and developments related to the benchmark activities and we invite as well authors who have performed similar work and developments outside of the UAM benchmark. Potential topics include, but are not limited to:

  • Status and progress of cross-section uncertainty (covariance) data in evaluated nuclear data files
  • Propagation of cross-section uncertainty data from evaluated nuclear data files to multigroup format including the input multigroup format of lattice physics codes
  • Propagation of multigroup cross-section uncertainty data to the input few-group format of core simulators
  • Evaluation of uncertainties associated with remaining few-group nodal homogenized data needed for core calculations—ADFs, form functions, CDFs, and so forth
  • Propagation and evaluation of kinetics and delayed neutron uncertainty data
  • Propagation of manufacturing uncertainties in few-group nodal homogenized data
  • Evaluation of uncertainties in the depletion calculation due to the basic nuclear data as well as the impact of processing the nuclear and covariance data
  • Propagation of few-group cross-section and other nodal homogenized data uncertainties in reactor core calculations
  • Solutions and comparative analysis of the test problems of Exercises I-1, I-2, and I-3 of OECD LWR UAM benchmark
  • Code and model uncertainties in reactor physics calculations

Before submission authors should carefully read over the journal's Author Guidelines, which are located at http://www.hindawi.com/journals/stni/guidelines/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/ according to the following timetable:


Articles

  • Special Issue
  • - Volume 2013
  • - Article ID 697057
  • - Editorial

Uncertainty Analysis in Reactor Physics Modeling

Kostadin Ivanov | Carlo Parisi | Oscar Cabellos
  • Special Issue
  • - Volume 2013
  • - Article ID 380284
  • - Research Article

Propagation of Cross-Section Uncertainties in Criticality Calculations in the Framework of UAM-Phase I Using MCNPX-2.7e and SCALE-6.1

C. J. Díez | J. J. Herrero | ... | J. S. Martínez
  • Special Issue
  • - Volume 2013
  • - Article ID 437409
  • - Research Article

Uncertainty Analysis of Light Water Reactor Fuel Lattices

C. Arenas | R. Bratton | ... | K. Ivanov
  • Special Issue
  • - Volume 2013
  • - Article ID 549793
  • - Research Article

PSI Methodologies for Nuclear Data Uncertainty Propagation with CASMO-5M and MCNPX: Results for OECD/NEA UAM Benchmark Phase I

W. Wieselquist | T. Zhu | ... | H. Ferroukhi
  • Special Issue
  • - Volume 2013
  • - Article ID 573697
  • - Research Article

SCALE Modeling of Selected Neutronics Test Problems within the OECD UAM LWR’s Benchmark

Luigi Mercatali | Kostadin Ivanov | Victor Hugo Sanchez
  • Special Issue
  • - Volume 2013
  • - Article ID 790206
  • - Research Article

Presentation and Discussion of the UAM/Exercise I-1b: “Pin-Cell Burn-Up Benchmark” with the Hybrid Method

O. Cabellos
  • Special Issue
  • - Volume 2013
  • - Article ID 426356
  • - Research Article

Uncertainty and Sensitivity Analyses of a Pebble Bed HTGR Loss of Cooling Event

Gerhard Strydom
  • Special Issue
  • - Volume 2012
  • - Article ID 767096
  • - Research Article

A Two-Step Approach to Uncertainty Quantification of Core Simulators

Artem Yankov | Benjamin Collins | ... | Thomas Downar
  • Special Issue
  • - Volume 2012
  • - Article ID 109614
  • - Research Article

Computational Method for Global Sensitivity Analysis of Reactor Neutronic Parameters

Bolade A. Adetula | Pavel M. Bokov
  • Special Issue
  • - Volume 2012
  • - Article ID 817185
  • - Research Article

Sensitivity Studies for the Exercise I-1 of the OECD/UAM Benchmark

E. Canuti | A. Petruzzi | ... | T. Kozlowski
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate33%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore0.810
Impact Factor1.082
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