| Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION codes HM Dalle, C Pereira, RGP Souza Annals of Nuclear Energy 29 (8), 901-912, 2002 | 42 | 2002 |
| Simulação do reator TRIGA IPR-R1 utilizando métodos de transporte por Monte Carlo HM Dalle Biblioteca Digital da Unicamp, 2005 | 33 | 2005 |
| Flux and dose rate evaluation of iter system using MCNP5 A Araújo, C Pereira, MAF Veloso, AL Costa, HM Dalle Brazilian Journal of Physics 40 (1), 58-62, 2010 | 27 | 2010 |
| Monte Carlo burnup simulation of the Takahama-3 benchmark experiment HM Dalle Proceedings of the 2009 International Nuclear Atlantic Conference, INAC2009 …, 2009 | 19 | 2009 |
| Enriched Gadolinium Burnable Poison for PWR Fuel-Monte Carlo Burnup Simulations of Reactivity HM Dalle, JRL de Mattos, MS Dias INTECH Open Access Publisher, 2013 | 16 | 2013 |
| Avaliação Neutrônica do Reator TRIGA IPR-R1 com Configuração de 63 Elementos Combustíveis e Barra de Regulação em F16 HM Dalle Restrict Document, CDTN/CNEN (NI–EC3-01/03), Belo Horizonte, Brazil, 2003 | 13 | 2003 |
| TRIGA IPR-R1 reactor simulation using Monte Carlo transport methods HM Dalle ScD Thesis, Universidade Estadual de Campinas, São Paulo (in Portuguese), 2005 | 8 | 2005 |
| Traceability from governmental producers of radiopharmaceuticals in measuring 18 F in Brazil AE Oliveira, A Iwahara, CJ Silva, PAL Cruz, R Poledna, RL Silva, ... Applied Radiation and Isotopes, 2015 | 6 | 2015 |
| Sensitivity Analysis of the TRIGA IPR-R1 Reactor Models Using the MCNP Code CAM Silva, JAD Salomé, BT Guerra, C Pereira, AL Costa, MAF Veloso, ... International Journal of Nuclear Energy 2014, 2014 | 6 | 2014 |
| MCNP5 modeling of the IPR-R1 TRIGA reactor for criticality calculation and reactivity determination CAM Da Silva, C Pereira, BT Guerra, MAF Veloso, AL Costa, HM Dalle, ... Nuclear Engineering and Design 241 (12), 4989-4993, 2011 | 6 | 2011 |
| Measured and calculated effective delayed neutron fraction of the IPR-R1 Triga reactor RMGP Souza, HM Dalle, DAM Campolina | 6 | 2011 |
| Validation of the Monteburns code for criticality calculations of TRIGA reactors HM Dalle, R Jeraj Research and Development Brazilian Journal, São Paulo 4 (2), 91-94, 2002 | 6 | 2002 |
| THE UTILIZATION OF IPR-R1 TRIGA NUCLEAR RESEARCH REACTOR FOR EDUCATIONAL PURPOSES IN BRAZIL AZ MESQUITA, R SOUZA, AV FERREIRA, HM DALLE, ACL COSTA | 6* | |
| Evaluation of the thermal neutron flux in samples of Al–Au alloy irradiated in the carrousel channels of the TRIGA MARK I IPR-R1 reactor using MCNP code JAD Salomé, BT Guerra, C Pereira, MÂBC de Menezes, CAM da Silva, ... Nuclear Engineering and Design 273, 576-583, 2014 | 5 | 2014 |
| Shielding simulation of the CDTN cyclotron bunker using MCNP HM Dalle, DAM Campolina | 4 | 2011 |
| Monte Carlo simulation of TRIGA IPR-R1: reactivity worth, burnup, flux and power HM Dalle, MA Veloso Proceedings of the 3rd World TRIGA Users Conference, 2006 | 4 | 2006 |
| Coolant channel distribution in the core of the IPR-R1 TRIGA nuclear reactor AZ Mesquita, AV Ferreira, ACL Costa, HM Dalle, DAP Palma 21st Brazilian Congress of Mechanical Engineering, October, 24-28, 2011 | 3 | 2011 |
| Instrumented Fuel Element Recovery in IPR-R1 TRIGA Nuclear Research Reactor AZ Mesquita, MA Cândido, AJ Pinto, HM Dalle Proceedings of COBEM 2009 20th International Congress of Mechanical …, 2009 | 3 | 2009 |
| Characterization of burned fuel of the TRIGA IPR-R1 research reactor using Monteburns code HM Dalle, R Jeraj, EB Tambourgi | 3 | 2002 |
| A Temperature Dependent ENDF/B-VI. 8 ACE Library for UO2, ThO2, ZIRC4, SS AISI-348, H2O, B4C and Ag-In-Cd HM Dalle, M Bianchini, PC Gomes Proceedings of the 2009 International Nuclear Atlantic Conference, 2009 | 2 | 2009 |
