Number of visits: 1127
Scientific publications of C.H.M. Broeders after his retirement 2007
Study of Sapphire and MgO as Thermal Neutron filters for The TRIGA Moroccan Reactor Beam ports,
International Journal of Advanced Research (2016), Volume4, Issue 7,560-567
MODEL-BASED GENERATION OF NEUTRON INDUCED FISSION
YIELDS UP TO 20 MEV BY THE GEF CODE,
PHYSOR 2014, Kyoto, Japan, September 28 - October 3, 2014
Study of sapphire and MgO as thermal neutron filters for the moroccan TRIGA research reactor beam,
ANIMMA 2013, Marseille, June 23-27 2013
Assessment of the Source Term in LWR in View of the Fukushima Accident,
Reaktortagung 2012, Stuttgart, May 22-24, 2012
Assessment of fission product yield data needs in
nuclear reactor applications,
PHYSOR 2012, Knoxville, Tennessee, April 15-20, 2012
Evaluation of Neutron Physics Parameters and
Reactivity Coefficients for Sodium Cooled Fast Reactors,
ICAPP 2010, San Diego, USA, June 13-17, 2010
MCNPX Monte Carlo burnup simulations of the correlation experiments in the NPP Obigheim,
Paper Annals of Nuclear Energy 37 (2010)
Final draft contribution to IAEA CRP ADS project, related to the correlation experiments in the NPP Obigheim,
Updated paper as prepared for final meeting Mumbay, February 2010
Investigations for the build-up of trans-uranics in the fuel of modern pressurized water reactors,
Reaktortagung 2009, Dresden, May 12-14, 2009
A new scientific solution for preventing the misuse of reactor-grade plutonium as nuclear explosive
Paper Nuclear Engineering and Design 238 November 2008
Auswirkungen von verschiedenen Brennstoffzyklusoptionen auf die anfallenden Aktinidenmengen im
deutschen Reaktorpark
Paper ATOMWIRTSCHAFT 53. Jg. (2008) Heft 6 Juni 2008
Last update 26.08.2016 by
C.H.M. Broeders.