Английская Википедия:Four factor formula
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Шаблон:Short description Шаблон:Refimprove The four-factor formula, also known as Fermi's four factor formula is used in nuclear engineering to determine the multiplication of a nuclear chain reaction in an infinite medium.
| Symbol | Name | Meaning | Formula | Typical thermal reactor value |
|---|---|---|---|---|
| <math>\eta</math> | Reproduction factor (eta) | Шаблон:Sfrac | <math> \eta = \frac{\nu \sigma_f^F}{\sigma_a^F} </math> | 1.65 |
| <math>f</math> | Thermal utilization factor | Шаблон:Sfrac | <math>f = \frac{\Sigma_a^F}{\Sigma_a}</math> | 0.71 |
| <math>p</math> | Resonance escape probability | Шаблон:Sfrac | <math>p \approx \exp \left( -\frac{\sum\limits_{i=1}^{N} N_i I_{r,A,i}}{\left( \overline{\xi} \Sigma_p \right)_{mod}} \right)</math> | 0.87 |
| <math>\epsilon</math> | Fast fission factor | Шаблон:Sfrac | <math>\varepsilon \approx 1 + \frac{1-p}{p}\frac{u_f \nu_f P_{FAF}}{f \nu_t P_{TAF} P_{TNL}}</math> | 1.02 |
The symbols are defined as:[2]
- <math>\nu</math>, <math>\nu_f</math> and <math>\nu_t</math> are the average number of neutrons produced per fission in the medium (2.43 for uranium-235).
- <math>\sigma_f^F</math> and <math>\sigma_a^F</math> are the microscopic fission and absorption cross sections for fuel, respectively.
- <math>\Sigma_a^F</math> and <math>\Sigma_a</math> are the macroscopic absorption cross sections in fuel and in total, respectively.
- <math>N_i</math> is the number density of atoms of a specific nuclide.
- <math>I_{r,A,i}</math> is the resonance integral for absorption of a specific nuclide.
- <math>I_{r,A,i} = \int_{E_{th}}^{E_0} dE' \frac{\Sigma_p^{mod}}{\Sigma_t(E')} \frac{\sigma_a^i(E')}{E'}</math>.
- <math>\overline{\xi}</math> is the average lethargy gain per scattering event.
- Lethargy is defined as decrease in neutron energy.
- <math>u_f</math> (fast utilization) is the probability that a fast neutron is absorbed in fuel.
- <math>P_{FAF}</math> is the probability that a fast neutron absorption in fuel causes fission.
- <math>P_{TAF}</math> is the probability that a thermal neutron absorption in fuel causes fission.
- <math>P_{TNL}</math> is the thermal non-leakage probability
Multiplication
The multiplication factor, Шаблон:Mvar, is defined as (see Nuclear chain reaction):
- <math>k = \frac{\mbox{neutron population following nth generation}}{\mbox{neutron population during nth generation}}</math>
- If Шаблон:Mvar is greater than 1, the chain reaction is supercritical, and the neutron population will grow exponentially.
- If Шаблон:Mvar is less than 1, the chain reaction is subcritical, and the neutron population will exponentially decay.
- If Шаблон:Math, the chain reaction is critical and the neutron population will remain constant.
In an infinite medium, neutrons cannot leak out of the system and the multiplication factor becomes the infinite multiplication factor, <math>k = k_{\infty}</math>, which is approximated by the four-factor formula.
See also
References
