microscopic vs macroscopic cross section

the microscopic cross sections for thermal neutrons. The cross sections averaged over the thermal neutron energy spectrum, /2 V /2A.

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He explains: “A microscopic cross section looks like brickwork, with flat, hexagonal tablets of a crystalline, calcium carbonate mineral stacked in neat layers. jw The distinction between macroscopic and microscopic cross - section is that the former is a property of a specific lump of material (with its density), while the latter is an intrinsic property of a type of nuclei.

5 Neutron reaction cross sections •Total microscopic neutron cross section is expressed as: σ= dN/dt / [(I/A) n A ∆x] • Defining neutron flux as: φ= I/A (neutrons/sec.cm2) • Then: dN/dt = φ(A ∆x n σ) • Neutron flux can also be defined: φ= nnvn where: nn is neutron density per cm3 in beam, vn relative velocity (cm/sec.) of neutrons in beam

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The microscopic cross-section “σ” is used to characterize the probability of reaction between a neutron and an individual particle or nucleus.

Formally, the equation above defines the macroscopic neutron cross-section (for reaction x) as the proportionality constant between a neutron flux incident on a (thin) piece of material and the number of reactions that occur (per unit volume) in that material. The distinction between macroscopic and microscopic cross-section is that the former

Figure 9 shows the variation of Sha factors with neutron energy for Pu microscopic cross sections for spherical particles for all 40 combinations of D and α. A 

Eq. (3.13) can be solved as soon as the energy-averaged macroscopic cross-sections are given. With the exception of the multi-group differential macroscopic scattering cross-section

S_nu = S_u234 + S_u235 + S_u238. Now since you already have the microscopic cross sections for each isotope, the only thing you need to do to get the macroscopic cross section is to find each number density, N_i. N_i = y_i * rho * N_a/M, where y_i is the atom fraction of isotope i in the natural uranium, rho is the density of the natural

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between microscopic, mesoscopic, and macroscopic flow models. from publication: State-of-the-art of vehicular traffic flow (11.2-mi) section of Autobahn 9 near Munich, Germany. These combined

The standard unit for measuring the cross section is the barn, which is equal to 10−28 m2 or 10−24 cm2. The 

233U. 233 U belongs to the group of fissile isotopes. It is produced by radiative neutron capture in nuclear reactors containing thorium fuel. 2. 236U. 236 U is neither a fissile isotope nor a fertile isotope. 236 U is fissionable only by fast neutrons. Isotope 236 U is formed in a nuclear reactor from fissile isotope 235 U.

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2/24 · macroscopic cross-section Sources: Orange Book, 2 nd ed., p. 217 [ Terms ] [ Book ] PAC, 1994, 66 , 2513. ( Nomenclature for radioanalytical chemistry (IUPAC Recommendations 1994) ) on page 2517 [ Terms ] [ Paper ]

4/24 · This is essentially barns per nucleon (proton). Now look at pp, which goes up to ~ 10 9 GeV (~10 18 eV). At these energies, neutron and proton cross sections are about the same (minimum ~ 40 mb per nucleon at 100 GeV). For silicon, I would multiply per nucleon cross sections by ~28 2/3 = 9.3 (geometric cross section). Bob S.

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2. Explain concept of cross section: σ(E), macroscopic cross section: Σ(E), mean free path 3. Explain rate laws for bulk power production from fission 4. Explain how to get information from on-line ENDF data bases.

Microscopic cross-sections (σ) are given for each nuclide usually in units of barns, where 1 b = 1 x 10-24 cm2. It is essentially the effective 

a. Write the definitions of the microscopic and macroscopic cross sections b. What is the inverse of the macroscopic cross-section signify in terms of interaction probability? c. If the macroscopic neutron scattering cross-section is 0.1 cm-1 , how far will a neutron travel on average before a collision will take place? d.

Microscopic Versus Macroscopic Cross Section. Up to now, the cross section referred to in this article corresponds to the microscopic cross section σ.However, it is possible to define the macroscopic cross section Σ which corresponds to the total "equivalent area" of all target particles per unit volume:. where N is the atomic density of target.

Total microscopic neutron cross section is expressed as: v n relative velocity (cm/sec.) of neutrons in beam. • Cross section σ can be experimentally 

Microscopic Versus Macroscopic Cross Section Up to now, the cross section referred to in this article corresponds to the microscopic cross section σ.However, it is possible to define the macroscopic cross section Σ which corresponds to the total “equivalent area” of all target particles per unit volume:

microscopic cross-section, σ ; probability. of a specified interaction or reaction between an incident radiation and a target particle or system of particles. It 

While the microscopic cross-sectionconveysinformationabout the probabilities ofscattering, absorption orfission for an individual nucleus, the calculation ofthe rates ofthese processes for the reactor as a whole involves, in addition. the numbers of atoms ofeachmaterial perunit volume ofthereactor.

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Microscopic cross-sections (σ) are given for each nuclide usually in units of barns, where 1 b = 1 x 10 -24 cm 2. It is essentially the effective area for the particular reaction. The macroscopic cross-section (Σ) has units of cm -1 is derived from the microscopic section according to Σ = N σ, where N is the atomic density of a particular nuclide.

There are two kinds of cross sections, microscopic and macroscopic. Microscopic cross section refer to cross sections of neutrons reacting with a specific 

v). Describe in general terms the variation of absorption cross-section of U-235 and U-238 with neutron energy. 3.3 THE MICROSCOPIC CROSS-. SECTION.