Browsing Department of Nuclear Engineering by Title
Now showing items 47-66 of 262
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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 ... -
The decontamination of radioactive ion exchange resins using neutral salts as elutriants
([Cambridge, Mass.] Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Delayed neutron assay to test sorbers for uranium-from-seawater applications
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1982, 1982) -
Demonstration of methods for analytical measurement of natural circulation flow in EBR-II
([Cambridge, Mass.] : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1986, 1986) -
Derivation of the diagonal 0-weighting method
([Cambridge, Mass.] : Nuclear Engineering, Massachusetts Institute of Technology, 1987, 1987) -
Description of the computer code 2DTD
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1976], 1976) -
Description of the two-dimensional nodal codes "NRMS," a multigroup static code, and "NRMT," a one- and two-group transient code for solution of the neutron diffusion equation in rectangular geometry
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1977], 1977) -
Design and fuel management of PWR cores to optimize the once-through fuel cycle
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering and Energy Laboratory ; Springfield, Va. : Available from National Technical Information Service, 1978, 1978) -
Design of a cold neutron source for the MIT reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1970, 1970) -
Design of a high-level waste repository system for the United States
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1988, 1988)This report presents a conceptual design for a High Level Waste disposal system for fuel discharged by U.S. commercial power reactors, using the Yucca Mountain repository site recently designated by federal legislation. ... -
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 ... -
Design, construction and evaluation of a facility for the simulation of fast reactor blankets
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)A facility has been designed and constructed at the MIT Reactor for the experimental investigation of typical LMFBR breeding blankets. A large converter assembly, consisting of a 20-cm-thick layer of graphite followed by ... -
Determination of thermal neutron capture gamma yields
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1969], 1969)A method of analysing Ge(Li) thermal neutron capture gamma spectra to obtain total gamma yields has been developed. Tie method determines both the yields from the well resolved gamma peaks in a spectrum as well as the gamma ... -
Deuterium concentration by chemically-refluxed ammonia-hydrogen exchange : Final report
(Cambridge, Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1969, 1969) -
Deuterium concentration by chemically-refluxed ammonia-hydrogen exchange : Supplementary reports
(Cambridge, Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1969, 1969) -
Development of utility system simulation model
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Development of utility system simulation model : progress report no. 2
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1971, 1971) -
Dynamic event tree analysis method (DETAM) for accident sequence analysis
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1991, 1991) -
Dynamic event trees in accident sequence analysis
(Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1990, 1990) -
Dynamics and control of nuclear rocket engines
(Cambridge, Mass. Massachusetts Institute of Technology, Nuclear Engineering Dept., 1960, 1960)