Neutron generation from T(d,n)

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Discussion Overview

The discussion centers around calculating the neutron generation rate from a T(d,n) reaction in a neutron generator. Participants are exploring the theoretical framework and equations necessary to determine the number of neutrons produced per second based on given parameters such as current, cross-section, and target area.

Discussion Character

  • Technical explanation
  • Homework-related
  • Debate/contested

Main Points Raised

  • One participant seeks assistance in finding the formula to calculate neutron production from a T(d,n) reaction, providing specific parameters including current, energy, and target characteristics.
  • Another participant inquires about the expression for the interaction or reaction rate for a monoenergetic beam of particles, mentioning the need to determine flux from current and target area.
  • A participant proposes an equation for the reaction rate, R = (I σ N) / s, and seeks confirmation of its correctness, expressing concerns over obtaining unexpected results.
  • One participant confirms the proposed equation is correct but suggests showing the calculations involved.
  • A later reply clarifies that the inquiry is related to a project rather than homework, indicating a significant discrepancy between calculated and expected neutron output, which raises questions about potential errors in the calculations.
  • The participant notes that typical generators produce around 10^8 neutrons per μA, contrasting with their calculated value of 6.3*10^7 neutrons.

Areas of Agreement / Disagreement

Participants generally agree on the equation for reaction rate, but there is disagreement regarding the accuracy of the calculated neutron output, with one participant expressing significant concern over the discrepancy between their results and expected values.

Contextual Notes

Participants have not resolved the underlying assumptions or potential errors in the calculations leading to the discrepancy in neutron output. The discussion does not clarify the definitions or conditions under which the proposed equation applies.

Xaritou
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Hi guys. I have a small question and i would appreciate your help.

I want to find how many neutrons per second (in 4π) are produced from a neutron generator. The generator works with T(d,n) reaction.. We have 0.5 mA d at 100keV energy that hits a target of titanium-tritium that has 2*10^20 nucleus of Tritium. The cross section of this reaction is around 5 barn..and the surface of the target is 5cm^2..

Can anyone help me by giving me the formula that i must use to solve the problem?

Thnx in advance
 
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Does one know the expression for the interaction or reaction rate for a monoenergetic beam of particles striking a target of atomic density N?

One is given a microscopic cross-section, σ, of the reaction, and one should be able to determine d flux from the current and beam/target area.
 
I am looking for the equation if anyone knows it. I found sth Like R= (I σ N) /s, where R= Reaction rate, N=the total number of Tritium nucleus, σ= the cross section for the reaction, I = the current of the d beam, and s= the surface of the target...

Can anyone confirm that this is correct, because i am getting strange results...
 
Xaritou said:
I am looking for the equation if anyone knows it. I found sth Like R= (I σ N) /s, where R= Reaction rate, N=the total number of Tritium nucleus, σ= the cross section for the reaction, I = the current of the d beam, and s= the surface of the target...

Can anyone confirm that this is correct, because i am getting strange results...
That's correct.

Perhaps one can show what one is doing with the equation.

BTW - this appears to be homework.
 
No.. Its not homework. Its about a project. I have to calculate theoretically the amount of neutrons the source produce per second, so we can be able to shield it correctly when it arrives. I am just getting 10^4 less neutrons than the generators specifications, and i want to know what i am doing wrong... I get 6.3*10^7 neutrons, when i suppost to get about 10^11.
Generally this kind of generators produce 10^8 neutrons per μΑ
 

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