Science and Technology of Nuclear Installations

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

Publishing date
23 May 2014
Submission deadline
03 Jan 2014

Lead Editor

1School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China

2Department of Nuclear Engineering, Texas A&M University, College Station, Texas, 77843-3133, USA

3Xian Jiaotong University, Xian, China

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


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 Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at according to the following timetable:


  • Special Issue
  • - Volume 2014
  • - Article ID 209747
  • - Editorial

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

Baowen Yang | Yassin A. Hassan | ... | Liangzhi Cao
  • Special Issue
  • - Volume 2014
  • - Article ID 635651
  • - Research Article

CFD Turbulence Study of PWR Spacer-Grids in a Rod Bundle

C. Peña-Monferrer | J. L. Muñoz-Cobo | S. Chiva
  • Special Issue
  • - Volume 2014
  • - Article ID 462460
  • - Research Article

Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments

Baowen Yang | Jianqiang Shan | ... | Hu Mao
  • Special Issue
  • - Volume 2014
  • - Article ID 247862
  • - Research Article

Effect of Flow Blockage on the Coolability during Reflood in a 2 2 Rod Bundle

Kihwan Kim | Byung-Jae Kim | ... | Chul-Hwa Song
  • Special Issue
  • - Volume 2014
  • - Article ID 301052
  • - Research Article

Subchannel Analysis of Wire Wrapped SCWR Assembly

Jianqiang Shan | Henan Wang | ... | Yang Jiang
  • Special Issue
  • - Volume 2014
  • - Article ID 120604
  • - Research Article

Direct Numerical Simulation and Visualization of Subcooled Pool Boiling

Tomoaki Kunugi | Yasuo Ose
  • Special Issue
  • - Volume 2014
  • - Article ID 602062
  • - Research Article

Influence of Spacer Grid Outer Strap on Fuel Assembly Thermal Hydraulic Performance

Jingwen Yan | Yuxiang Zhang | ... | Yuemin Zhou
Science and Technology of Nuclear Installations
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Acceptance rate24%
Submission to final decision110 days
Acceptance to publication14 days
Journal Citation Indicator0.380
Impact Factor1.1
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