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:

Science and Technology of Nuclear Installations
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Acceptance rate24%
Submission to final decision110 days
Acceptance to publication14 days
CiteScore1.500
Journal Citation Indicator0.380
Impact Factor1.1
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