F. E. Dunn

发表

The role of SASSYS-1 in LMR (Liquid Metal Reactor) safety analysis

T.Y.C. Wei, F. E. Dunn, 1988 .

EVALUATION OF THERMAL CONDUCTION BETWEEN TWO SUBCHANNELS WITH A COMPUTATIONAL FLUID DYNAMICS CODE

Yong-Bum Lee, Dohee Hahn, James E. Cahalan, 2004 .

Decay heat calculations for transient analysis

F. E. Dunn, 1989 .

Physics and safety studies of a low conversion ratio sodium cooled fast reactor.

James E. Cahalan, M. A. Smith, F. E. Dunn, 2004 .

MNSR transient analyses and thermal hydraulic safety margins for HEU and LEU cores using the RELAP5-3D code

J. E. Matos, F. E. Dunn, J. Thomas, 2008 .

ACCEPTABILITY OF LOCAL BOILING DURING SHUTDOWN HEAT REMOVAL

F. E. Dunn, 1985 .

The SASSYS LMFBR systems analysis code

F. E. Dunn, Frederick G. Prohammer, 1984 .

Whole core sub-channel analysis in LMR systems codes, current status

Dohee Hahn, James E. Cahalan, F. E. Dunn, 2005 .

Verification and implications of the multiple-pin treatment in the SASSYS-1 liquid-metal reactor systems analysis code

F. E. Dunn, 1996 .

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

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