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Data analysis : operating crew characteristics and interactions during steam generator tube rupture simulation
(Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1990, 1990)
This report provides an analysis of the data collected during a one-month visit to a 2-unit, non-U.S. PWR. The data consist of results from interviews (largely with plant operators and former shift engineers) and from ...
LMFBR Blanket Physics Project progress report no. 2
(Cambridge, Mass., Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971], 1971)
LMFBR Blanket Physics Project progress report no. 3
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)
LMFBR Blanket Physics Project progress report no. 4
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1973], 1973)
LMFBR Blanket Physics Project progress report no. 7
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)
Heavy water lattice project annual report / editors: T.J. Thompson ... [et al.] ; contributors J. Barch ... [et al.]
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1965], 1965)
Studies of epithermal neutrons in uranium, heavy water lattices
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1964, 1964)
Measurements related to reactor physics parameters were made in three heavy water lattices. The three lattices studied consisted of 0.250-inch-diameter, 1.03 w/o U2 3 5 uranium fuel rods arranged in triangular arrays and ...
Reactor physics calculation of BWR fuel bundles containing gadolinia
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1977], 1977)
A technique for the calculation of the neutronic behavior of BWR fuel bundles has been developed and applied to a Vermont Yankee fuel bundle. The technique is based on a diffusion theory treatment of the bundle, with ...
Design of central irradiation facilities for the MITR-II research reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976], 1976)
Design analysis studies have been made for various in-core irradiation facility designs which are presently used, or proposed for future use in the MITR-II. The information obtained includes reactivity effects, core flux ...
Availability of the THERMIT thermal hydraulic reactor computer codes through M.I.T.
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1981], 1981)
Three of the THERMIT thermal hydraulic reactor computer codes are available through the Department of Nuclear Engineering at MIT. The three available codes are THERMIT-2, for LWR subchannel analysis, THIOD, for BWR analysis ...