Thermal Neutron Absorption Rate in Water?

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Homework Help Overview

The problem involves calculating the rate of thermal neutron absorption in water, given a specific neutron flux in a reactor context. The subject area pertains to nuclear physics and neutron interactions with matter.

Discussion Character

  • Exploratory, Assumption checking, Conceptual clarification

Approaches and Questions Raised

  • Participants discuss the relationship between neutron absorption rates and neutron flux, with some suggesting the mean free path of absorption as a relevant factor. Questions arise regarding the definitions and calculations of cross sections and atom density in relation to the problem.

Discussion Status

Participants are exploring various aspects of the problem, including the need for specific relationships and definitions. Some have referenced external materials for further understanding, while others express uncertainty about how to apply the information provided in their textbooks.

Contextual Notes

There are mentions of the mean free path and absorption cross sections, with participants noting a lack of detailed information in their resources. The discussion also touches on the differences in atom density calculations for molecules versus individual atoms.

bran_1
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Homework Statement


"The 2200 m/s flux in an ordinary water reactor is 1.5*10^13 neutrons/cm^2*s. At what rate are the thermal neutrons absorbed by the water?"

Homework Equations


(unsure)

The Attempt at a Solution


I know that absorption of a thermal neutron (a neutron in thermal equilibrium) is a type of radiative capture, and is therefore exothermic and considered an absorption reaction.

Where I'm stuck is how I can relate this information to the flux at the given neutron energy (velocity), as I don't see how I can get anywhere with the information given.

Any and all help would be greatly appreciated!
 
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bran_1 said:
Any and all help would be greatly appreciated!

you must get a relation between the rate of absorption and the generated flux of neutrons in water medium in say a reactor..

pl. consult your textbook.

i think the relation ship will involve the 'mean free path of absorption' and
for water, heavy water, graphite its given in nuclear reactor data table.
 
drvrm said:
you must get a relation between the rate of absorption and the generated flux of neutrons in water medium in say a reactor..

pl. consult your textbook.

i think the relation ship will involve the 'mean free path of absorption' and
for water, heavy water, graphite its given in nuclear reactor data table.

I have consulted it, it doesn't seem to elaborate beyond the definition of the mean free path. There is nothing mentioned about the mean free path of absorption
 
bran_1 said:
I have consulted it, it doesn't seem to elaborate beyond the definition of the mean free path. There is nothing mentioned about the mean free path of absorption
i have seen discussion in the following reference...<.http://nvlpubs.nist.gov/nistpubs/jres/51/jresv51n4p203_a1b.pdf >i think you can use the introduction to understand and apply the process of neutron absorption in water
 
drvrm said:
i have seen discussion in the following reference...<.http://nvlpubs.nist.gov/nistpubs/jres/51/jresv51n4p203_a1b.pdf >i think you can use the introduction to understand and apply the process of neutron absorption in water

So based on that:

absorption = n * v / lambda ,
lambda = 1 / sigma,
sigma = lowercase_sigma * N,
phi = n * v = flux

I'm given the flux, but how would I get lowercase_sigma? Also, I know N to be the atom density, so how does that change for a molecule vs an atom, since the units are in neutrons/cm^3?
 
bran_1 said:
I'm given the flux, but how would I get lowercase_sigma? Also, I know N to be the atom density, so how does that change for a molecule vs an atom, since the units are in neutrons/cm^3?

if you wish to have cross section for neutron absorption then you can use the absorption data .
moreover N the no. of atoms/nuclei involved can also be calculated using avogadro number and density of water.

you may see a text (ref given below) which discusses the shielding and the variation of cross sections with neutron energy
<http://mragheb.com/NPRE 402 ME 405 Nuclear Power Engineering/Neutron Cross Sections.pdf>
 

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