1. Impact of PWR spent fuel variations on back-end features of advanced fuel cycles with TRU-fueled VHTRs;Alajo;Annals of Nuclear Energy,2011
2. Design status of the HTR 500 power plant and the HTR module power plant;Arndt,1989
3. A general description of the lattice code WIMS;Askew;Journal of the British Nuclear Engineering Society,1966
4. Cardoso, F., 2008. Reatores Avançados de Alta Temperatura: Avaliação neutrônica preliminar utilizando os códigos WIMSD e MCNP. Master Thesis. Brazilian University of Minas Gerais, UFMG, Brazil.
5. A neutronic evaluation of reprocess fuel and depletion study of VHTR using MCNPX and WIMSD5 code;Cardoso,2011