J. R. Deen

发表

Transient analyses and thermal-hydraulic safety margins for the Greek Research Reactor (GRRI)

W. L. Woodruff, J. R. Deen, C. Papastergiou, 1995 .

A feasibility study for LEU conversion of the WWR-SM research reactor in Uzbekistan.

J. E. Matos, N. A. Hanan, A. Rakhmanov, 2001 .

Validation of the WIMSD4M cross-section generation code with benchmark results

W. L. Woodruff, J. R. Deen, L. E. Leal, 1995 .

Neutronic feasibility studies using U-Mo dispersion fuel (9 Wt % Mo, 5.0 gU/cm{sup 3})for Leu conversion of the Maria (Poland), IR-8(Russia), and WWR-SM (Uzbekistan) research reactors.

J. E. Matos, M. M. Bretscher, N. A. Hanan, 2000 .

Neutronic feasibility studies for LEU conversion of the HFR Petten Reactor.

J. E. Matos, N. A. Hanan, J. R. Deen, 2000 .

Analyses of Greek Research Reactor with mixed HEU-LEU Be reflected core

J. L. Snelgrove, J. R. Deen, K. Papastergiou, 1993 .

Alternative Fuel Cycle Options : Performance Characteristics and Impact on Nuclear Power Growth Potential

C. E. Till, R. R. Rudolph, J. R. Deen, 1977 .

WIMS-D4M user manual

W. L. Woodruff, J. R. Deen, C. I. Costescu, 1995 .

A neutronic feasibility study for LEU conversion of the IR-8 research reactor.

J. R. Deen, 1998 .

Measurement of Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Californium-252 Fission-Neutron Spectrum

J. R. Deen, E. Draper, 1975 .