The finite element method for neutron diffusion problems in hexagonal geometry

Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975

Bibliographische Detailangaben
Hauptverfasser:	Wei, Thomas Ying Chung, Hansen Kent F.
Weitere Verfasser:	Massachusetts Institute of Technology. Department of Nuclear Engineering
Format:	Technical Report
Veröffentlicht:	Cambridge, [Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1975 2014
Schlagworte:	TK9008.M41 N96 no.173 Finite element method Neutron transport theory Nuclear reactors > Computer programs Nuclear reactor kinetics
Online Zugang:	http://hdl.handle.net/1721.1/89495

Online

http://hdl.handle.net/1721.1/89495