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Subchannel Analysis, CFD Modeling and Verifications, CHF Experiments and Benchmarking

Call for Papers

As one of the most active areas of nuclear thermal-hydraulics, research on subchannel analysis, CFD modeling and verifications, CHF experiments and benchmarking is of great concern to the nuclear fuel design and reactor safety. With the difficulty and high cost involving large scale rod bundle CHF experiment for light water reactors, the CFD modeling and development have become the major trend in predicting the local conditions in the complicated subchannel geometry. We invite investigators to contribute original research articles as well as review papers that will cover single and two-phase experimental measurements, CHF testing and benchmarking, subchannel analysis, V& V/UQ, CFD development, modeling, and verifications. We are particularly interested in articles describing recent progress of innovative experimental research on fuel assembly CHF testing. Potential topics include, but are not limited to:

  • Recent Development in fuel design tools, benchmarking, and verification techniques:
    • Recent development in subchannel codes and subchannel analysis
    • T/H and neutronic coupling
    • CFD modeling and benchmarking
  • CHF testing and verifications: Fuel assembly CHF testing—post-Columbia University HTRF
    • Initial facility benchmarking and certification
    • Long term continued data verification process(recertification)
    • QA/QC and CHF data qualification/verifications
    • Other issues involving CHF tests (low pressure, low flow, etc.)
  • Mechanistic modeling and empirical DNB correlations for BWR & PWR fuel
    • Local and nonlocal phenomena
    • Development and application of mechanistic models
    • Development and application of empirical correlations
    • Integral approach combining CFD and subchannel analysis
  • Effect of parameters on CHF
    • Parametric study: Heated length, hydraulic diameter, mixing coefficient, and so forth
    • Axial and radial flux distribution
    • Transients
    • Transposition from experimental geometry to full bundle assembly
  • Reactor core protection against DNB
    • Uncertainties, margins, criteria, and so forth
    • Statistical methods
    • Digital and analogue methodologies (ΔT protection and on-line DNBR calculations)
  • Fuel reliability and inspection

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/submit/journals/stni/sac/ according to the following timetable:

Manuscript DueFriday, 3 January 2014
First Round of ReviewsFriday, 28 March 2014
Publication DateFriday, 23 May 2014

Lead Guest Editor

  • Baowen Yang, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China

Guest Editors

  • Yassin A. Hassan, Department of Nuclear Engineering, Texas A&M University, College Station, Texas, 77843-3133, USA
  • Jianqiang Shan, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China
  • Bin Zhang, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China
  • Junli Gou, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China
  • Liangzhi Cao, Xian Jiaotong University, Xian, China