proceedings:1995_igorr4 [IGORR]

23-25 May 1995 - Gatlinburg TN, USA

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