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The neutron transport equation is a balance statement that conserves neutrons. Each term represents a gain or a loss of a neutron, and the balance, in essence, claims that neutrons gained equals neutrons lost. It is formulated as follows: [1]
The intensity field can in principle be solved from the integrodifferential radiative transfer equation (RTE), but an exact solution is usually impossible and even in the case of geometrically simple systems can contain unusual special functions such as the Chandrasekhar's H-function and Chandrasekhar's X- and Y-functions. [3]
Download as PDF; Printable version; ... a a = symmetry/asymmetry extent coefficient for the numbers of neutrons ... These equations need to be refined such that the ...
This involves computing exact or approximate solutions of the transport equation, and there are various forms of the transport equation that have been studied. Common varieties include steady-state vs time-dependent, scalar vs vector (the latter including polarization), and monoenergetic vs multi-energy (multi-group).
Monte Carlo N-Particle Transport (MCNP) [2] is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation transport code designed to track many particle types over broad ranges of energies and is developed by Los Alamos National Laboratory.
A continuity equation is the mathematical way to express this kind of statement. For example, the continuity equation for electric charge states that the amount of electric charge in any volume of space can only change by the amount of electric current flowing into or out of that volume through its boundaries.
Diffusion cloud chamber with tracks of ionizing radiation (alpha particles) that are made visible as strings of droplets. In dosimetry, linear energy transfer (LET) is the amount of energy that an ionizing particle transfers to the material traversed per unit distance.
Geometric buckling is a measure of neutron leakage and material buckling is a measure of the difference between neutron production and neutron absorption. [1] When nuclear fission occurs inside of a nuclear reactor, neutrons are produced. [1] These neutrons then, to state it simply, either react with the fuel in the reactor or escape from the ...