| Title | Author(s) | Session |
| Status of the research reactor FRJ-2 at the Research Center Juelich, Germany | Wolters, J. | Technical session |
| Proceedings of the fourth meeting of the International Group On Research Reactors | Rosenbalm, K.F. | Technical session |
| Potential for new societal contributions from the advanced test reactor | Ryskamp, John M. Conner, Julie E. Ingram, Fred W. | Technical session |
| Absorber rigs - A better concept than burnable poison | Nielsen, Kirsten Hjerrild | Technical session |
| The initial criticality and nuclear commissioning test program at HANARO | Lee, Choong-Sung Seo, Chul-Gyo Jun, Byung-Jin | Technical session |
| Description of the high flux isotope reactor and future upgrades | Flanagan, G.L. | Technical session |
| Surveillance programme and upgrading of the High Flux Reactor Petten | Bieth, Michel | Technical session |
| Neutrons down-under: Australia's research reactor review | Murray, Allan | Technical session |
| Upgrade and modernization of NBSR | Williams, Robert E. | Technical session |
| ORPHEE reactor. Upgrade of the installation | Farnoux, B. , Maziere, M. | Technical session |
| Status of the FRM-II project | Boening, K. Hennings, U. | Technical session |
| Development of the new Canadian Irradiation-Research Facility | Lidstone, R.F. Lee, A.G. Bishop, W.E. Talbot, E.F. MCilwain, H. | Technical session |
| The state of the PIK reactor construction | Konoplev, K.A. | Technical session |
| A continuously pulsed TRIGA reactor: An intense source for neutron scattering experiments | Whittemore, William L. | Technical session |
| Status of ANS closeout activities | West, C.D | Technical session |
| Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods | Lee, A.G. Wilkin, G.B. | Technical session |
| Selected thermal and hydraulic experimentation in support of the advanced neutron source reactor | Yoder, G.L. Jr. Crabtree, J.A. Felde, D.K. McDuffee, J.L. Siman-Tov, M. Stovall, T.K. Swinson, W.F. Yahr, J.T. | Technical session |
| CHF correlation scheme proposed for research reactors using plate-type fuel - New CHF correlation under CCFL condition | Kaminaga, Masanori Sudo, Yukio Kodaira, Tsuneo Ohnishi, Nobuaki | Technical session |
| Thermal hydraulic tests of a liquid hydrogen cold neutron source. NISTIR 5026 | Siegwarth, J.D. Olson, D.A. Lewis, M.A. Rowe, J.M. Williams, R.E. Kopetka, P. | Technical session |
| Modeling and analysis of liquid deuterium-water reactions | Taleyarkhan, R.P. | Technical session |
| Advances in the understanding of U3Si2-Al dispersion fuel irradiation behavior | Snelgrove, J.L. Hofman, G.L. Rest, J. Birtcher, R.C. | Technical session |
| Status of development: Main features of plates and dummy element fabrication for FRM II | Ailloud, C. Colomb, P. Durand, J.P. Harbonnier, G. | Technical session |
| Dual fuel gradient development update | Pace, Brett W. | Technical session |
| The effects of irradiation to 8x1026m-2 on the mechanical properties of 6061-T651 aluminum | Alexander, D.J. | Technical session |
| MOCUP: MCNP-ORIGEN2 coupling utility programs | Babcock, R.S. | Technical session |
| Graphical user interface simplifies MCNP use and provides burnup capabilities | Lewis, Bryan | Technical session |
| Fission product and chemical energy releases during core melt events in U-Al research reactors | Taleyarkhan, R.P. | Technical session |
| Fission product release from the molten research reactor core, FRM-II | Didier, H.-J. | Technical session |
| JAERI/ORNL tests and analyses on transient heating of U3Si2-Al miniplates in nuclear safety research reactor | Fuketa, T. | Technical session |
| IGORR-IV workshop on R and D needs | Boening, Klaus | Technical session |