Synthesis of calculational methods for the design and analysis of radiation shields for nuclear rocket systems. Volume II. Analysis of radiation measurements in a nuclear rocket propellant tank mockup using simulated liquid hydrogen

Synthesis of calculational methods for the design and analysis of radiation shields for nuclear rocket systems. Volume II. Analysis of radiation measurements in a nuclear rocket propellant tank mockup using simulated liquid hydrogen [electronic resource]

Nesdps Office Of Nuclear Energy Space And Defense Power Systems.

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Bibliographic Details
Online Access:	Online Access
Corporate Authors:	Westinghouse Electric Corporation. Astronuclear Laboratory (Researcher), United States. Department of Energy. Technical Information Center (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Oak Ridge, Tenn. : Oak Ridge, Tenn. : United States. Dept. of Energy. Technical Information Center ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1968.
Subjects:	Polyethylenes. Computer Calculations. shielding > Radiation Transport. Thermal Neutrons. Fast Neutrons. nerva Reactor > Shielding. Simulation. Neutron Flux. Radioactivation. Monte Carlo Method. Gamma Dosimetry. Dose Rates. Radiation Protection. Planning.

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Call Number:	E 1.99:wanl-pr(ll)--022(vol.2)
E 1.99:wanl-pr(ll)--022(vol.2)	Available