Volume 24 (2024)
Volume 23 (2023)
Volume 22 (2022)
Volume 21 (2021)
Volume 20 (2020)
Volume 19 (2019)
Volume 18 (2018)
Volume 17 (2017)
Volume 16 (2016)
Volume 15 (2015)
Volume 14 (2014)
Volume 13 (2013)
Volume 12 (2012)
Volume 11 (2011)
Volume 10 (2010)
Volume 9 (2009)
Volume 8 (2008)
Volume 7 (2007)
Volume 6 (2006)
Volume 5 (2005)
Volume 4 (2004)
Volume 3 (2002)
Volume 2 (2000)
Volume 1 (1996)
Keywords = MCNPX
Number of Articles: 3
Neutronic and thermohydraulic analysis of annular fuels in MCNPX and ANSYS FLUENT for use in BNPP
Volume 24, Issue 4, March 2025, Pages 355-374
Monte Carlo simulation of response function of organic scintillators to gamma rays and neutrons using FLUKA, MCNPX and SCINFUL code
Volume 17, Issue 5, February 2018, Pages 635-645
Investigation of Isfahan miniature neutron source reactor (MNSR) for boron neutron capture therapy by MCNP simulation
Volume 14, Issue 4, January 2015, Pages 327-339