| Oxidation of aluminum alloy cladding for research and test reactor fuel YS Kim, GL Hofman, AB Robinson, JL Snelgrove, N Hanan Journal of Nuclear Materials 378 (2), 220-228, 2008 | 87 | 2008 |
| A Comparison of the PARET/ANL and RELAP5/MOD3 Codes for the Analysis of IAEA Benchmark Transients WL Woodruff, NA Hanan, RS Smith, JE Matos Argonne National Lab.(ANL), Argonne, IL (United States), 1996 | 75 | 1996 |
| A Monte Carlo burnup code linking MCNP and REBUS NA Hanan Argonne National Lab., 1998 | 32 | 1998 |
| A comparison of the RELAP5/MOD3 and PARET/ANL codes with the experimental transient data from the SPERT-IV D-12/25 series WL Woodruff, NA Hanan, JE Matos | 24 | 1997 |
| Comparative validation of Monte Carlo codes for the conversion of a research reactor VP Alferov, AI Radaev, MV Shchurovskaya, GV Tikhomirov, NA Hanan, ... Annals of Nuclear Energy 77, 273-280, 2015 | 22 | 2015 |
| The Russian ARGUS solution reactor HEU-LEU conversion: LEU fuel preparation, loading and first criticality PP Boldyrev, VS Golubev, SV Myasnikov, AK Pavlov, NV Petrunin, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2014 | 19 | 2014 |
| The use of WIMS-ANL lumped fission product cross sections for burned core analysis with the MCNP Monte Carlo code NA Hanan, RB Pond, WL Woodruff, MM Bretscher, JE Matos | 18 | 1998 |
| An alternative LEU design for the FRM-II NA Hanan, SC Mo, RS Smith, JE Matos | 18 | 1996 |
| Comparison of the FRM-II HEU design with an alternative LEU design SC Mo, NA Hanan, JE Matos | 17 | 2004 |
| Prediction model for oxide thickness on aluminum alloy cladding during irradiation YS Kim, GL Hofman, NA Hanan, JL Snelgrove | 15 | 2003 |
| Neutronic performance of the WWR-M research reactor in Ukraine RB Pond, NA Hanan, JE Matos, Y Mahlers, A Dyakov | 14 | 2002 |
| Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors M Kalimullah, AP Olson, EE Feldman, N Hanan, SH Pham, DS Yoon Argonne National Lab.(ANL), Argonne, IL (United States), 2020 | 12 | 2020 |
| A neutronic feasibility study for LEU conversion of the IR-8 research reactor. JR Deen Argonne National Lab., IL (US), 1998 | 10 | 1998 |
| A neutronic feasibility study for LEU conversion of the WWR-SM research reactor in Uzbekistan A Rakhmanov Argonne National Lab., 1998 | 10 | 1998 |
| Feasibility analysis for LEU conversion of the WWR-K reactor using an eight-tube uranium dioxide fuel assembly F Arinkin, P Chakrov, L Chekushina, S Gizatulin, K Kadyrzhanov, ... | 9 | 2005 |
| A neutronic feasibility study for LEU conversion of the Budapest research reactor. RB Pond Argonne National Lab., IL (US), 1998 | 9 | 1998 |
| Neutronic performance of several LEU fuel assembly designs for the WWR-SM research reactor in Uzbekistan MM Bretscher, NA Hanan, JE Matos, BS Yuldashev, S Baytelesov, ... | 8 | 2002 |
| Neutronic safety parameters and transient analyses for Poland's MARIA research reactor MM Bretscher, NA Hanan, JE Matos, K Andrzejewski, T Kulikowska | 8 | 1999 |
| A review of the Oconee-3 probabilistic risk assessment N Hanan NUREG/CR-4374, 1986 | 8 | 1986 |
| A review of the Shoreham Nuclear Power Station probabilistic risk assessment D Ilberg, K Shiu, N Hanan, E Anavim NUREG/CR-4050, 1985 | 8 | 1985 |
