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Items Found: 31
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Your Search: (SUBJECT=Neutrons)
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CEMM/GEMMD Library/Gulf Breeze,FL
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(N,alpha) Reactions on Heavy Nuclei Induced by 14.2-Mev Neutrons.
Burn-out of Cadmium Shields.
Calibration of the Bonner Ball Neutron Detectors Used at the Tower Shielding Facility.
Circular Polarization of gamma Rays.
Computation of the Shielding Thickness Required to Reduce a Neutron Flux or a Dose Rate to a Given Value.
Contribution to Research on the Behavior of Fission Products in Nuclear Fuels by Measurement of the Vapor Pressures of the Constituents of (Upu)O/Sub 2/ Irradiated in a Fast Neutron Flux.
Critical Review of the Energy Released in Nuclear Fission.
Demetra Program Set for Calculating Problems of Neutron Thermalization in the One-Dimensional Cell of a Heterogeneous Reactor by the Quasi-Diffusion Method.
Determination of the Activation Cross-Section of Short Lived Nuclear Isomers for Thermal Neutrons.
Dredged sediment movement tracing in San Francisco Bay utilizing neutron activation /
Evidence for a Kpi Resonance Near 1750 Mev/C/Sup 2/.
Final States with Three Charged Particles and a Visible Anti K/Sup 0/ from K/Sup -/D Interactions at 4.5 Gev/C.
Fission Fragment Angular Distributions for /Sup 230/TH, /Sup 232/TH, /Sup 231/PA, and /Sup 239/Pu.
Fracture and Tensile Behavior of Neutron-Irradiated A533-B Pressure Vessel Steel.
Fuel Element Development for the Gas-Cooled Fast Breeder Reactor. Part I. Sealed Fuel Rod Design.
Integral Transport Equation in One-Dimensional Cylindrical Geometry. Polynomial Approximation and Linear Anisotropic Scattering. Part II. Characteristics and Numerical Applications of the Shadok Code- Possible Extension of the Method.
Ionizing radiation. Part 1, X- and gamma ([gamma])-radiation, and neutrons.
K* (890) Production in the Charge Exchange Reaction K/Sup +/n Yields K/Sup +/pi/Sup -/P at 9 Gev/C.
K* (890) Production in the Charge Exchange Reaction K/Sup +/n Yields K/Sup +/pi/Sup -/P at 9.1 Gev.
Linear Accelerator Project. Progress Report, October 1-December 31, 1970.
Measurement of absorbed dose of neutrons, and of mixtures of neutrons and gamma rays : Recommendations of the
Monitoring in the vadose zone : a review of technical elements and methods /
Neutron contamination from medical electron accelerators : recommendations of the National Council on Radiation Protection and Measurements.
Neutron Energy-Dependent Capture gamma-Ray Yields in Tantalum and Tungsten.
Preparation and Separation of Carrier-Free /Sup 131/CS from Irradiated Baco/Sub 3/.
Protection against neutron radiation up to 30 million electron volts.
Scattering Length of the n-n Reaction.
Study of Nucleon-Nucleon Interaction from the 3 Nucleon Interaction D(N,Nnp) at 14 Mev.
Study of the Overlap Conditions Required in Sequential Discrete Ordinates Transport Calculations for a 14-Mev Neutron Source in a 5000-M Radius Cylinder of Air.
Tonagrid - a Monte Carlo Program for Calculation of Neutron and Photon Transport in Ducts.
Water Resources Research Program: Transport and Dispersion of Oil-Refinery Wastes in the Coastal Waters of Southwestern Lake Michigan (Experimental Design: Sinking-Plume Condition).
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