What are the sources of neutrons in starting up a nuclear reactor?

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Discussion Overview

The discussion focuses on the sources of neutrons necessary for starting up a nuclear reactor, particularly in the context of critical accidents. Participants explore various neutron sources, their mechanisms, and implications for reactor operation.

Discussion Character

  • Technical explanation
  • Exploratory
  • Debate/contested

Main Points Raised

  • One participant expresses uncertainty about the role of neutrons in fission during critical accidents and questions the initial sources of neutrons.
  • Another participant mentions that neutrons are always present due to spontaneous fission and cosmic rays, suggesting that reactors typically have sufficient neutrons during operation.
  • A different participant explains that the fuel itself undergoes natural decay, releasing neutrons at a steady rate, which contributes to the fission process in reactors.
  • Several sources of neutrons for reactor startup are proposed, including Cf-252, which spontaneously fissions to release neutrons, and Antimony-beryllium or Pu-Be sources that produce neutrons through alpha reactions.
  • It is noted that as fuel is irradiated, isotopes like Pu-240 and U-238 contribute to neutron production through spontaneous fission, although there is some uncertainty regarding the extent of these contributions.
  • One participant asserts that after a reactor core has been irradiated, it may have enough background neutrons to eliminate the need for external neutron sources, although this has not been tested in practice.
  • Another participant counters that cores do not require a new neutron source after being through one cycle, as previously burned fuel provides sufficient neutrons.

Areas of Agreement / Disagreement

Participants present multiple competing views regarding the necessity and sources of neutrons for reactor startup, indicating that the discussion remains unresolved with differing opinions on the role of various neutron sources.

Contextual Notes

Some claims depend on specific conditions, such as the state of the fuel and the reactor's operational history. There is also uncertainty regarding the magnitude of contributions from certain neutron production mechanisms.

tiepngh
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Thank for all if you understand my ideal.
My problem is i don't know what's neutron which cause of fission in critical accident?
seem it must be have the first neutrons, and then reaction fission occurred ?
eg The critical model in some nuclear accident, what is neutron source?
The nuclear bomb? ...
thanks...
 
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There are always some neutrons just floating around. Spontaneous fission and cosmic rays are examples.

Also what kind of accident are you concerned about. Reactors are going all the time, so there are plenty of neutrons. Accident means it got out of control somehow.
 
The fuel itself is decaying naturally, releasing neutrons. In a reactor the fuel is arranged in such a way that the neutrons cause MORE decays, but even a small amount by itself is releasing neutrons at a fairly steady rate.
 
forward:Sorry i Can't include a link
There are several sources of neutrons for starting up a reactor:

a) Cf-252 spontaneously fissions and thereby releases neutrons.
Small wires of Cf-252 are inserted into selected fuel assemblies
(the spontaneous fission rate is so high that only gram amounts
of Cf-252 are needed).

b) Antimony-berylium or Pu-Be sources are also used. In these sources,
the Antimony or the Plutonium emits a high-energy alpha which
is absorbed by the Berylium which then emits a neutron, among
other things.
c) As the fuel is irradiated, Pu-240 builds up. It also spontaneously
fissions, giving rise to neutrons. There are some spontaneous
fissions in U-238 as well. I seem to recall that there may be some
(alpha, n) reactions directly in the fuel, although I am uncertain
as to the magnitude of this contribution.
It is likely that after a core has been irradiated it has enough background
neutrons that the Cf-252 and berylium sources are no longer needed. So
far as I know, however, no one has put this theory to the test in a power
reactor.
 
googlefans said:
forward:Sorry i Can't include a link
There are several sources of neutrons for starting up a reactor:

a) Cf-252 spontaneously fissions and thereby releases neutrons.
Small wires of Cf-252 are inserted into selected fuel assemblies
(the spontaneous fission rate is so high that only gram amounts
of Cf-252 are needed).

b) Antimony-berylium or Pu-Be sources are also used. In these sources,
the Antimony or the Plutonium emits a high-energy alpha which
is absorbed by the Berylium which then emits a neutron, among
other things.
c) As the fuel is irradiated, Pu-240 builds up. It also spontaneously
fissions, giving rise to neutrons. There are some spontaneous
fissions in U-238 as well. I seem to recall that there may be some
(alpha, n) reactions directly in the fuel, although I am uncertain
as to the magnitude of this contribution.
It is likely that after a core has been irradiated it has enough background
neutrons that the Cf-252 and berylium sources are no longer needed. So
far as I know, however, no one has put this theory to the test in a power
reactor.

Cores do not need a new neutron source after being through one cycle unless they are starting with completely fresh fuel. The once and second burned fuel provides enough neutrons to not require a new neutron source. This isn't a theory, this is actual practice.
 

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