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LMFBR RADIATION TRANSPORT METHODS DEVELOPMENT.

Authors: Mynatt, F. R.; Gritzner, M. L.; Williams, L. R.; Clifford, C. E.;

LMFBR RADIATION TRANSPORT METHODS DEVELOPMENT.

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United States
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Keywords

Numerical Solution, Neutrons, Gamma Radiation/Shielding For, Gamma Radiation, Waste Processing & Radiation Protection, N78130* --Power Reactor Development--Containment Systems, Liquid Metal Fast Breeder Reactor/Shielding For, Fftf Reactor, Shielding/Development Of Fast Neutrons, Calculation Methods For, Dose Rates, Sodium Cooled Reactors Neutrons, Fast Neutrons, Calculation Of Neutron And Gamma Dose Rates Through Lead, Planning, Fbr Type Reactors, Shielding, Fast Test Reactor/Shielding For, Calculation Methods For Development Of, Configuration, Fast/Shielding For

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selected citations
These citations are derived from selected sources.
This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Citations provided by BIP!
popularity
This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.
BIP!Popularity provided by BIP!
influence
This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).
BIP!Influence provided by BIP!
impulse
This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.
BIP!Impulse provided by BIP!
0
Average
Average
Average