Searched:  Author Contains ("Deen, J. R.") Sorted By:  Relevance, Descending Results:  1–20 of exactly 20 matches. in 0.266 seconds. Sort Results By: Relevance Publication Date System Entry Date Resource/Doc Type Title Research Org Sponsoring Org OSTI Identifier Creator/Author(s) Ascending Descending Return to Original Search Page Page 1 of 1     Show only (√) Items Clear all (√) Items Printer Friendly Refine Search   Size Identifier Title Creator/Author (s) Pub Date 680 K ANL/TD/CP-97537 A neutronic feasibility study for LEU conversion of the IR-8 research reactor. Deen, J. R. 1998 Oct 22 288 K CONF-8510102-6 Reduced-reactivity-swing LEU fuel cycle analyses for HFR Petten Deen, J.R. ; Snelgrove, J.L. 1985 Jan 01 317 K CONF-8410173-9 Neutronics study of LEU fuel options for the HFR-Petten Deen, J.R. ; Snelgrove, J.L. 1984 Jan 01 396 K CONF-861185-6 Preliminary LEU fuel cycle analyses for the Belgian BR2 reactor Deen, J.R. ; Snelgrove, J.L. 1986 Jan 01 284 K CONF-8809221-8 LEU fuel cycle analyses for the Belgian BR2 Research Reactor Deen, J.R. ; Snelgrove, J.L. 1988 Jan 01 941 K CONF-821155-2 Measurements and analysis of critical assemblies for research reactors with mixed enrichments Deen, J.R. ; Snelgrove, J.L. ; Hobbs, R.W. 1982 Jan 01 931 K ANL/TD/CP-102956 Neutronic feasibility studies for LEU conversion of the HFR Petten Reactor. Hanan, N. A. ; Deen, J. R. ; Matos, J. E. 2000 Sep 26 463 K ANL/TD/CP-102883 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. Bretscher, M. M. ; Deen, J. R. ; Hanan, N. A. ; et.al. 2000 Sep 18 821 K ANL/TD/CP-100107 Neutronic safety and transient analyses for potential LEU conversion of the IR-8 research reactor. Deen, J. R. ; Hanan, N. A. ; Smith, R. S. ; et.al. 1999 Sep 27 3 Mb ANL/RERTR/TM--23 WIMS-D4M user manual Deen, J.R. ; Woodruff, W.L. ; Costescu, C.I. 1995 Jul 01 571 K ANL/EP/CP--77803; CONF-9209266--2 Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel Deen, J.R. ; Snelgrove, J.L. ; Papastergiou, C. 1992 Dec 31 674 K ANL/TD/CP--85106; CONF-9409107--7 Validation of the WIMSD4M cross-section generation code with benchmark results Deen, J.R. ; Woodruff, W.L. ; Leal, L.E. 1995 Jan 01 1 Mb ANL/TD/CP--85125; CONF-9409107--4 Relative performance properties of the ORNL Advanced Neutron Source Reactor with reduced enrichment fuels Bretscher, M.M. ; Deen, J.R. ; Hanan, N.A. ; et.al. 1994 Dec 31 748 K ANL/EP/CP--81441; CONF-9310185--7 New ENDF/B-V nuclear data library for WIMS-D4M Deen, J.R. ; Woodruff, W.L. ; Costescu, C.I. 1993 Dec 31 900 K ANL/EP/CP--81423; CONF-9310185--9 Analyses of Greek Research Reactor with mixed HEU-LEU Be reflected core Deen, J.R. ; Snelgrove, J.L. ; Papastergiou, K. 1993 Dec 31 1 Mb CONF-950420--14 Validation of the WIMSD4M cross-section generation code with benchmark results Leal, L.C. ; Deen, J.R. ; Woodruff, W.L. 1995 Feb 01 646 K ANL/TD/CP--85128; CONF-9409107--9 Transient analyses and thermal-hydraulic safety margins for the Greek Research Reactor (GRRI) Woodruff, W.L. ; Deen, J.R. ; Papastergiou, C. 1995 Feb 01 675 K ANL/EP/CP-77800; CONF-9209266--4 A comparison of WIMS-D4 and WIMS-D4m generated cross-section data with Monte Carlo Woodruff, W.L. ; Deen, J.R. ; Costescu, C.I. 1992 Jan 01 571 K ANL/EP/CP-77803; CONF-9209266--2 Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel Deen, J.R. ; Snelgrove, J.L. ; Papastergiou, C. 1992 Jan 01 675 K ANL/EP/CP--77800; CONF-9209266--4 A comparison of WIMS-D4 and WIMS-D4m generated cross-section data with Monte Carlo Woodruff, W.L. ; Deen, J.R. ; Costescu, C.I. 1992 Nov 01 Top Return to Original Search Page Page 1 of 1