Maxwell-Boltzmann distribution.

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SUMMARY

The discussion focuses on the Maxwell-Boltzmann distribution as it pertains to neutrons in thermal equilibrium within reactor cores, specifically in Light Water Reactors (LWRs) and Pressurized Water Reactors (PWRs). Key temperature ranges are identified, with PWR inlet temperatures between 275°C and 293°C and exit temperatures reaching up to 330°C. The conversation highlights the significance of neutron flux estimation for energies below 1 eV, particularly in relation to the thermal and fast neutron behavior in various reactor types. The moderator-to-fuel volume ratio is approximately 1:1, and the discussion references specific reactor designs and their thermal characteristics.

PREREQUISITES
  • Understanding of Maxwell-Boltzmann distribution principles
  • Knowledge of neutron behavior in thermal reactors
  • Familiarity with Light Water Reactor (LWR) and Pressurized Water Reactor (PWR) designs
  • Basic concepts of thermal equilibrium and energy dependence in nuclear physics
NEXT STEPS
  • Research neutron flux estimation techniques for thermal reactors
  • Study the impact of temperature variations on neutron behavior in PWRs and BWRs
  • Explore the role of moderator-to-fuel volume ratios in reactor efficiency
  • Investigate the thermal characteristics of different fuel types, particularly UO2
USEFUL FOR

Nuclear engineers, reactor physicists, and anyone involved in the design or analysis of nuclear reactors, particularly those focusing on neutron behavior and thermal dynamics in LWRs and PWRs.

Nucengable
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Any one has some links, papers... anything describes the maxwell-boltzmann distribution that characterize neutrons in thermal equilibrium with the reactor core material at specific temperature...?
I want to get a crude estimation of energy-dependence neutrons flux for energies below 1 eV.
 
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Neutrons slow down in the water (in an LWR) which in a PWR has an inlet temperature of about 275 to 293°C, and an exit temperature of about 300 to 327°C (up to 330°C in the hot channel). In a BWR, the inlet is about 274°C and the exit temperature is at saturation of the core pressure, so the temperature is about 274 to 276°C. BWRs can use spectral shift in which flow is reduced to increase voiding, and that leads to under-moderation which hardens the spectrum which allows for resonance capture in U-238.

The fuel is hotter, typically about 400°C on the pellet periphery, and with a centerline temperature of ~900 to 1400°C depending on the linear power. The average fuel temperature is in between ~700 to 800°C.

The moderator to fuel volume is about 1:1 give or take.
 
http://tannerm.com/maxwell_boltzmann.htm
As Astronuc notes, the temperatures vary quite a bit - [STRIKE]fuel pellets in a working reactor reach close to the melting point of UO2 at the center of the pellets (by design)[/STRIKE], and the coolant enters at 275°C (548 K) and exits at 319°C (592 K) in an ACR (for example), the moderator is maintained much cooler.
Furthermore, the neutrons are born at very high speeds - typically ~2 MeV; a significant portion of the neutrons will be fast.
http://www.neimagazine.com/journals/Power/NEI/September_2004/attachments/NEISept04p26-35.pdf is a fuel bundle description for various reactors; choose the data for your type and run the numbers.

But, if you were to assume a homogenous reactor at the mean temperature, you would have an order of magnitude estimate. A Westinghouse bundle, for instance, is 214mmx214mm, and has 264 8.19mm dia fuel rods; if it was fully loaded, it would be 30% fuel - but the flow channel is only 60%, the other 10% is the gap and wall. Call it .3 * 1000K, .6 * 570K, .1 * 620K so mean temperature is ~700K.
 
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