Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Natural Sciences, Nuclear Engineering, Physics +13

Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics

Alberto Sartori, Davide Baroli, Antonio Cammi et al. · Annals of Nuclear Energy · 2014 · 48 citations · Full text

Engineering, Nuclear Engineering, Chemical Kinetics +13

Benchmark evaluation of reactor critical parameters and neutron fluxes distributions at zero power for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP

A. Borio di Tigliole, Antonio Cammi, M. Clemenza et al. · Progress in Nuclear Energy · 2009 · 47 citations

Engineering, Nuclear Engineering, Physics +16

TRIGA reactor absolute neutron flux measurement using activated isotopes

A. Borio di Tigliole, Antonio Cammi, D. Chiesa et al. · Progress in Nuclear Energy · 2013 · 42 citations · Full text

Engineering, Nuclear Engineering, Physics +10

Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core

D. Chiesa, M. Clemenza, M. Nastasi et al. · Annals of Nuclear Energy · 2015 · 27 citations

Engineering, Nuclear Engineering, Physics +14