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Analysis of conventional and plutonium recycle unit-assemblies for the Yankee (Rowe) PWR
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1971], 1971)
An analysis and comparison of Unit Conventional UO2 Fuel-Assemblies and proposed Plutonium Recycle Fuel Assemblies for the Yankee (Rowe) Reactor has been made. The influence of spectral effects, at the watergaps -and ...
Investigation of solution techniques for large sparse band width matrix equations of linear systems
(Cambridge, [Mass.] : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, 1976, 1976)
Analysis of operating data related to power and flow distribution in a PWR
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1974], 1974)
The analysis of the effects of the uncertainties associated with temperature and power measurements in the Connecticut Yankee Reactor leads to the evaluation of the uncertainty associated with the effective flow factor. ...
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)
An improved long range fuel management program
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1978, 1978)
The effect of refueling decisions and engineering constraints on the fuel management for a pressurized water reactor
([Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering] 1974, 1974)
The decontamination of radioactive ion exchange resins using neutral salts as elutriants
([Cambridge, Mass.] Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971)
Sensitivity analysis of the reactor safety study
(Cambridge [Mass.] : Massachusetts Institute of Technology, Energy Laboratory, 1979, 1979)
Variational derivation of modal-nodal finite difference equations in spatial reactor physics
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)
A class of consistent coarse mesh modal-nodal approximation methods is presented for the solution of the spatial neutron flux in multigroup diffusion theory. The methods are consistent in that they are systematically derived ...
Pressurized water reactor loss-of-coolant accidents by hypothetical vessel rupture
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1972, 1972)