Chapter 4<strong>The</strong>ory/Models4.1 Transport equationPhenomena in radiation physics and particle transport <strong>of</strong> leptons, baryons, mesons andenergetic photons can be described by the Boltzmann integro-differential equation settledin 1872. <strong>The</strong> equation will be briefly described here, because Monte-Carlo and deterministicapproaches employ solutions <strong>of</strong> the equation for neutron and gamma-transport. Itis a continuity equation in phase space consisting <strong>of</strong> three space coordinates, the kineticenergy and the direction <strong>of</strong> motion. Solutions <strong>of</strong> the Boltzmann equation which hereare just briefly presented in order in introduce some nomenclature are evaluated in moredetail in the literature for reactor physics [Eme69] and for fusion technology [Dol82]. <strong>The</strong>non-relativistic Boltzmann equation can be written as( )1 ∂ ˙Φiv i ∂t=++I{ }} {− ⃗ Ω∇ ˙Φ iII{ }} {∑[∫ ∫jIII{ }}]{S[ ∂ ˙Φi∂E − ˙Φ i2Eσ ij(⃗x, E B → E, ⃗ Ω B → ⃗ Ω ) ˙Φj(⃗x, E B , ⃗ Ω B , t ) dE B d ⃗ Ω B ]− σ i (⃗x, E) ˙Φ iIV{ }} {ln 2− ˙Φi + ∑ ln 2b ijvE 1/2,i jV{ }} {+ Y i (⃗x, E, Ω,vE ⃗ t) (4.1)1/2,iwhere ˙Φ i (⃗x, E, ⃗ Ω, t) is the angular dependent unknown flux, i.e. the number <strong>of</strong> particles<strong>of</strong> type i in the volume element dxdydz at ⃗x at time t, in the energy element dE at Ewith a direction <strong>of</strong> motion within dΩ at ⃗ Ω, multiplied by the speed v i <strong>of</strong> the particle. Itgives the number <strong>of</strong> particles per cm 2 , per MeV, per steradian and per second at a givenlocation at a given time.(I) the first term in Eq. 4.1 reflects the translation/reduction <strong>of</strong> the phase space−div [ ⃗ Ω ˙Φi (⃗x, E, ⃗ Ω, t) ] = − ⃗ Ω∇ ˙Φ i .(II) considers the particle nucleus interaction (energy, angle and particle type are changed).σ ij(⃗x, E B → E, ⃗ Ω B → ⃗ Ω ) is the macroscopic cross section for the production <strong>of</strong> i-35
36 CHAPTER 4. THEORY/MODELStype particles with space coordinates (⃗x, E, ⃗ Ω) as a result <strong>of</strong> a collision <strong>of</strong> a j-typeparticle with phase space coordinates (⃗x, E B , ⃗ Ω B ). σ i (⃗x, E) is the macroscopic totalcollision cross section.(III) S is the “stopping power” which describes how particles lose energy continuously atrate S per unit path length. <strong>The</strong> density distribution <strong>of</strong> particles with energy E B is˙Φ i (⃗x, E B , ⃗ Ω B , t)S(⃗x, E B ) and after slowing down to energy E: ˙Φi (⃗x, E, ⃗ Ω B , t)S(⃗x, E).(IV) represents particle decay: E 1/2,i is the half life <strong>of</strong> particle i. b ij is the branching ratio<strong>of</strong> the decay channel leading to particle i from particle j.(V) Y i is the external source term (e.g. a particle beam, neutrons from an α − n sourceor photons from radioactive material).Equation 4.1 is a system <strong>of</strong> coupled transport equations, which is, in general difficult tosolve. Solving the equation for hadronic cascades is more difficult than, for instance, forneutrons in the core <strong>of</strong> a nuclear reactor because <strong>of</strong> secondary particle production. Thusthe solution involves solving the fluxes for many different particle types. In the following,some <strong>of</strong> the most useful quantities characterizing the radiation field are listed:<strong>The</strong> integral quantity (actually used to define the angular flux ˙Φ i (⃗x, E, Ω, ⃗ t) in units<strong>of</strong> [cm −2 s −1 sr −1 eV −1 ] is the fluence ˙Φ i (⃗x)∫ ∫˙Φ i (⃗x) = dE d ⃗ ∫Ω ˙Φ i (⃗x, E, Ω, ⃗ t) (4.2)E 4π t<strong>The</strong> <strong>of</strong>ficial definition <strong>of</strong> fluence by the International Commission on Radiation Unitsand Measurements (ICRU, 1993) [icru93] is based on crossing <strong>of</strong> a surface anddefines the fluence as the quotient <strong>of</strong> dN by dα, where dN is the number <strong>of</strong> particlesincident on a sphere <strong>of</strong> cross sectional area dα, ˙Φi (⃗x) = dN/dα. This definition isthe source <strong>of</strong> frequent mistakes. It is not to be interpreted as “flow” or “flux” <strong>of</strong>particles through a surface, but to be understood as a density <strong>of</strong> particle path-lengthin an infinitesimal volume: ˙Φi (⃗x) = lim ∆V →0∑i s i /∆V [cm× cm −3 =cm −2 ], where∑i s i is the sum <strong>of</strong> path-length segments. <strong>The</strong> fluence is therefore a measure <strong>of</strong> theconcentration <strong>of</strong> the particle path in an infinitesimal volume element around a spacepoint. If the particle’s path-length is measured in units <strong>of</strong> mean free path λ = 1/σ,the expression <strong>of</strong> fluence is equivalent to the density <strong>of</strong> collisions σ ˙Φ i (⃗x). <strong>The</strong> mostimportant fluence estimator (which was also applied in sect. 3.2, is the track-lengthestimator which represents the average fluence in a space region when the sum <strong>of</strong>track-lengths is divided by the volume). Frequently the fluence is calculated becauseit is proportional to the effect <strong>of</strong> interest, since many effects can be expressed asvolume concentrations <strong>of</strong> some quantity proportional to the “number <strong>of</strong> collisions”.<strong>The</strong> fluence rate or flux density also referred to as scalar flux is expressed in terms<strong>of</strong> the sum <strong>of</strong> path segments transversed within a given volume per time unit∫˙Φ i (⃗x, t) = dΩ⃗ ∫dE ˙Φ i (⃗x, E, Ω, ⃗ t) (4.3)4πIn Monte-Carlo calculations with a source given in units <strong>of</strong> particles per unit timethe scalar flux represents a fluence quality.E