Browsing Dept. of Nuclear Engineering Technical Reports by Title
Now showing items 185-204 of 262
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Optimization of material distributions in fast breeder reactors
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Optimization of the axial power shape in pressurized water reactors
(Cambridge, Mass. : Massachusetts Institute of Technology, Energy Laboratory, 1981, 1981)Analytical and numerical methods have been applied to find the optimum axial power profile in a PWR with respect to uranium utilization. The preferred shape was found to have a large central region of uniform power density, ... -
Organic moderator-coolant in-pile irradiation loop for the MIT nuclear reactor
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1961, 1961) -
Physical dependencies in accident sequence analysis
(Cambridge, MA : Nuclear Engineering Dept., Massachusetts Institute of Technology, 1989, 1989) -
PL-MODT and PL-MODMC : two codes for reliability and availability analysis of complex technical systems using the fault tree modularization technique
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1978], 1978)The methodology used in the PL-MOD code has been extended to include the time-dependent behavior of the fault tree components. Four classes of components are defined to model time-dependent fault tree leaves. Mathematical ... -
Pressurized water reactor loss-of-coolant accidents by hypothetical vessel rupture
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1972, 1972) -
Process system requirements of the MIT reactor at five megawatts
([Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962], 1962) -
Processing incentives for Russian weapons-grade plutonium
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1997], 1997) -
Prompt activation analysis for boron and lithium
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963) -
Prompt activation analysis of coal and iron ore
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1971, 1971) -
Proposed methods for determining the effect of U-236 and Np-237 on the value of uranium as feed for pressurized water power reactors / by D.A. Goellner and M. Benedict
(Cambridge, Mass. : Dept. of Nuclear Engineering, Massachusetts Institute of Technology, [1966], 1966) -
PULSE : an IBM 7094 program for calculation of fast neutron kinetics by Monte Carlo. Addendum no. 1, May 1964
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1964, 1964) -
PULSE : an IBM 7094 program for calculation of fast neutron kinetics by Monte Carlo. Progress report, October, 1963
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1963, 1963) -
Quantitative methods for assessing nuclear fuel cycle diversion resistance
(Cambridge, Mass. : Massachusetts Institute of Technology, [Dept. of Nuclear Engineering], 1979, 1979) -
Rate of exchange of deuterium between water and dissolved hydrogen in presence of diethylamine
(Cambridge, Mass. Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1964, 1964) -
The Reactivity and transient analysis of MITR-II
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1972], 1972)The two-dimensional, time dependent, three-group diffusion equations for the proposed designed core of the MIT reactor are written with an extra source term accounting for the photoneutrons generated in the D20 reflector. ... -
The Reactor engineering of the MITR-II : construction and startup
(Cambridge : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1976, 1976)The heavy water moderated and cooled research reactor, MITR-I, has been replaced with a light water cooled, heavy water reflected reactor called the MITR-II. The MITR-II is designed to operate at 5 thermal megawatts. The ... -
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 ... -
The reactor physics of the Massachusetts Institute of Technology reactor redesign
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)An H20 cooled compact MITR-II core, reflected by D20 has been designed for the MITR to increase the reflector thermal neutron flux at tips of beam ports by a factor of 3 or better, without changing the operating power level ... -
Reactor physics project final report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1970], 1970)This is the final report in an experimental and theoretical program to develop and apply single- and few-element methods for the determination of reactor lattice parameters. The period covered by the report is January 1, ...