F. Dunn

发表

Evaluation of the conduction shape factor with a CFD code for a liquid–metal heat transfer in heated triangular rod bundles

J. Cahalan, Yong-bum Lee, D. Hahn, 2007 .

Thermal fatigue due to beam interruptions in a Lead-Bismuth cooled ATW blanket

F. Dunn, 2000 .

Evaluation of a uranium zirconium hydride fuel rod option for conversion of the MIT research reactor (MITR) from highly-enriched uranium to low-enriched uranium

E. Feldman, C. Wang, K. Sun, 2017 .

Liquid-metal-cooled reactor thermal-hydraulic calculations in the United States

F. Dunn, D. Mohr, D. Malloy, 1988 .

Advanced burner test reactor preconceptual design report.

P. J. Finck, James E. Cahalan, Yu Tang, 2008 .

The STAT7 Code for Statistical Propagation of Uncertainties In Steady-State Thermal Hydraulics Analysis of Plate-Fueled Reactors

E. Wilson, F. Dunn, L. Hu, 2016 .

Power distributions in fresh and depleted LEU and HEU cores of the MITR reactor.

F. E. Dunn, J. G. Stevens, Lin-Wen Hu, 2012 .

Preliminary safety evaluation of the advanced burner test reactor.

James E. Cahalan, F. E. Dunn, T. H. Fanning, 2006 .