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 = MCNP code
Number of Articles: 5
Calculation of Radiation Damage for Simulation of Neutron Radiation Damage by Ion Irradiation and Development AMTRACK Program.
Volume 18, Issue 2, September 2018, Pages 251-261
Determination of the dead layer and full-energy peak efficiency of an HPGe detector using the MCNP code and experimental results
Volume 16, Issue 4, February 2017, Pages 375-381
A polynomialâbased function approach to point isotropic gamma-ray buildup factor data in double layered spherical shield of water and lead
Volume 13, Issue 4, March 2014, Pages 383-389
Investigation of reactivity variations of the Isfahan MNSR reactor due to variations in the thickness of the core top beryllium layer using WIMSD and MCNP codes
Volume 10, Issue 3, December 2010, Pages 273-280
Investigation of reactivity changes due to flooding the irradiation sites of the MNSR reactor using the MCNP code and comparison with experimental results
Volume 10, Issue 1, June 2010, Pages 55-61