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NEPA Project quarterly progress report, April 1--June 30, 1950

Description: Exploration of various types of power plant cycles for nuclear propelled aircraft has been continued during this quarter. The principal current objective of the project is the development of information which will make an intelligent choice of the basic power plant cycle possible. It is still hoped that this choice can be made late in 1950. The survey studies which have been under way for several months continued during the quarter. These consist of analyses and rough preliminary layouts for various types of aircraft, using each of the several basic cycles which have been seriously considered for each of the three phases of development. Although it is still extremely premature to discuss the relative merits of the various cycles, the information so for developed discloses some cycle differences which may, if confirmed by additional work, be significant. In this respect, there have been no recent major changes in the comparative standings of the cycles.
Date: December 31, 1950
Partner: UNT Libraries Government Documents Department

THEORETICAL ESTIMATE OF MAXIMUM POSSIBLE NUCLEAR EXPLOSION

Description: The maximum nuclear accident which could occur in a Na-cooled, Be moderated, Pu and power producing reactor is estimated theoretically. (T.R.H.) 2O82 Results of nuclear calculations for a variety of compositions of fast, heterogeneous, sodium-cooled, U-235-fueled, plutonium- and power-producing reactors are reported. Core compositions typical of plate-, pin-, or wire-type fuel elements and with uranium as metal, alloy, and oxide were considered. These compositions included atom ratios in the following range: U-23B to U-235 from 2 to 8; sodium to U-235 from 1.5 to 12; iron to U-235 from 5 to 18; and vanadium to U-235 from 11 to 33. Calculations were performed to determine the effect of lead and iron reflectors between the core and blanket. Both natural and depleted uranium were evaluated as the blanket fertile material. Reactors were compared on a basis of conversion ratio, specific power, and the product of both. The calculated results are in general agreement with the experimental results from fast reactor assemblies. An analysis of the effect of new cross-section values as they became available is included. (auth)
Date: January 31, 1950
Creator: Bethe, H.A.
Partner: UNT Libraries Government Documents Department