Science and Technology of Nuclear Installations

Selected Papers from OECD-NEA PSBT Benchmark


Publishing date
28 Dec 2012
Status
Published
Submission deadline
06 Jul 2012

1University of Michigan, 2945 Cooley Building, 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109-2104, USA

2Pennsylvania State University, 231 Reber Building, University Park, PA 16802, USA

3McMaster University, 1280 Main Street West, Hamilton, ON, Canada, L8S 4K1

4Technical University of Madrid, Avenida Arco de la Victoria s/n, 28040 Madrid, Spain

5San Piero a Grado Research Group (GRNSPG), University of Pisa, 56126 Pisa, Italy


Selected Papers from OECD-NEA PSBT Benchmark

Description

The International OECD/NRC PWR Subchannel and Bundle Test (PSBT) benchmark (http://www.oecd-nea.org/science/wprs/egrsltb/PSBT/) encourages advancement in subchannel analysis of fluid flow in rod bundles. The aim of this benchmark is to assess and compare numerical models for the prediction of detailed subchannel void distributions and departure from nucleate boiling (DNB) to full-scale experimental data on a prototypical PWR rod bundle. The benchmark activity is an international project supported by US NRC and METI (Japan) and endorsed by the OECD/NEA.

Participants in the OECD-NEA PSBT benchmark are strongly encouraged to submit research and review papers summarizing their predictions and results. Potential topics include, but are not limited to:

  • System code simulations: authors should clearly identify the models employed (e.g., two-fluid: 6 equations) as well as the constitutive relationships employed
  • Subchannel code simulations: authors should identify the models employed (e.g., 4- or 5-equation drift-flux as well as lateral momentum models) as well as the constitutive relationships and other assumptions (e.g., mixing models and coefficients)
  • Computational fluid dynamics (CFD): authors should identify the nodalization and models employed (e.g., wall boiling and interface models) as well as any additional closure models

Authors should also provide a description of the basic numerical methods, discretization details and grid, and closure relationships.

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 2014
  • - Article ID 694016
  • - Editorial

Selected Papers from OECD-NEA PSBT Benchmark

Maria Avramova | Annalisa Manera | ... | Alessandro Petruzzi
  • Special Issue
  • - Volume 2013
  • - Article ID 946173
  • - Review Article

Overview and Discussion of the OECD/NRC Benchmark Based on NUPEC PWR Subchannel and Bundle Tests

M. Avramova | A. Rubin | H. Utsuno
  • Special Issue
  • - Volume 2013
  • - Article ID 725687
  • - Research Article

Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database

M. Avramova | A. Velazquez-Lozada | A. Rubin
  • Special Issue
  • - Volume 2013
  • - Article ID 508485
  • - Research Article

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

Maria Avramova | Diana Cuervo
  • Special Issue
  • - Volume 2012
  • - Article ID 757356
  • - Research Article

OECD/NRC PSBT Benchmark: Investigating the CATHARE2 Capability to Predict Void Fraction in PWR Fuel Bundle

A. Del Nevo | D. Rozzia | ... | F. D’Auria
  • Special Issue
  • - Volume 2012
  • - Article ID 863503
  • - Research Article

Evaluation of ASSERT-PV V3R1 against the PSBT Benchmark

Kenneth H. Leung | David R. Novog
  • Special Issue
  • - Volume 2012
  • - Article ID 746467
  • - Research Article

Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

Taewan Kim | Victor Petrov | ... | Simon Lo
  • Special Issue
  • - Volume 2012
  • - Article ID 436142
  • - Research Article

Analysis of the NUPEC PSBT Tests with FLICA-OVAP

Matteo Bucci | Philippe Fillion
  • Special Issue
  • - Volume 2012
  • - Article ID 939561
  • - Research Article

CFD Analysis of a Void Distribution Benchmark of the NUPEC PSBT Tests: Model Calibration and Influence of Turbulence Modelling

E. Krepper | R. Rzehak
  • Special Issue
  • - Volume 2012
  • - Article ID 524598
  • - Research Article

Numerical Study of the Steady-State Subchannel Test-Case with NEPTUNE_CFD for the OECD/NRC NUPEC PSBT Benchmark

C. Baudry | M. Guingo | ... | M. Boucker
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate32%
Submission to final decision60 days
Acceptance to publication39 days
CiteScore1.700
Impact Factor0.825
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