N0AH

Author:	Lellouche, Gerald S.
Year:	1969
Document Type:	BNLA
Issuing Agency:	Brookhaven National Laboratory,
SUDOC:	Y 3.At 7:22/BNL-50157 (T-523)
Series:	TID ;
Report Number:	4500
Subjects:	Neutron flux
	Nuclear reactors--Computer programs
	FORTRAN IV (Computer program language)
	Neutron tranport theory
Link:	https://hdl.handle.net/2027/mdp.39015086581637