Open AccessBURNUP: A FORTRAN IV CODE FOR COMPUTING U AND Pu FUEL BURNUP FROM U, Pu, AND Nd MASS SPECTROMETRIC MEASUREMENTS UPDATED TO INCLUDE FAST REACTOR FUELS.
Author(s) -
B.F. Rider,
C.P. Ruiz,
J.P. Jr. Peterson,
T.V. McLaughlin
Publication year - 1970
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4012525
Subject(s) - burnup , fortran , nuclear engineering , code (set theory) , radiochemistry , computer science , environmental science , chemistry , engineering , operating system , programming language , set (abstract data type)
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