Browsing Department of Nuclear Engineering by Title
Now showing items 188-207 of 262
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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, ... -
Reactor physics project progress report
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1968, 1968) -
Reactor physics project progress report no. 2
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, [1969], 1969)This is the second annual report in an experimental and theoretical program to develop and apply single and few element heterogeneous methods for the determination of reactor lattice parameters. During the period covered ... -
Recalculation of power costs for the CANDU reactor
([Cambridge, Mass.] : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1962, 1962)