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Discover Neutron Transport Theory
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Neutron Diffusion
5.0
1 votes
Nuclear-reactor analysis
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Diffco - a computer code for calculating diffusion coefficients
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Nuclear reactor theory
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On application of variational methods to neutron transport in slabs
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Tables of the functions x(c₁-[greek letter nu]) and x¹(c₁,c₂) for the numerical solution of slab geometry neutron transport problems
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Neutron capture in the atmosphere from high altitude point sources
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Equation of state and transport measurements on expanded liquid metals up to 8000êK and 0.4 GPa
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On the concept of the transport mean path in kinetic theory
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A relativity primer for particle-transport
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Supply Chain Construction
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MCNP
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Computational methods for two-phase flow and particle transport
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Reactor physics
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A new moments solution to the neutron transport equation
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User's guide and description of the perturbation code modules DGRAD and TPERT
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The MENE neutron transport code
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User's guide and description of the perturbation code modules DGRAD and TPERT
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Monte-Carlo methods and applications in neutronics, photonics, and statistical physics
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Analytic functions and distributions in physics and engineering
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The iterative behavior of diffusion theory flux eigenvalue neutronics problems
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Slabbo- a discrete ordinate neutron transport code in plane geometry with anisotropic scattering
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Numerical solution of the one velocity Boltzmann neutron transport equation in slab geometry
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Krylov sub-space methods for K-eigenvalue problem in 3-D multigroup neutron transport
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