Delayed neutron

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In

fission products
(or actually, a fission product daughter after beta decay), any time from a few milliseconds to a few minutes after the fission event. Neutrons born within 10−14 seconds of the fission are termed "prompt neutrons".

In a

strong nuclear force
and thus either happens at fission, or nearly simultaneously with the beta decay, immediately after it. The various half lives of these decays that finally result in neutron emission, are thus the beta decay half lives of the precursor radionuclides.

Delayed neutrons play an important role in

nuclear reactor control
and safety analysis.

Principle

Delayed neutrons are associated with the beta decay of the fission products. After prompt fission neutron emission the residual fragments are still neutron rich and undergo a beta decay chain. The more neutron rich the fragment, the more energetic and faster the beta decay. In some cases the available energy in the beta decay is high enough to leave the residual nucleus in such a highly excited state that neutron emission instead of gamma emission occurs.

Using

thermal neutrons, and the immediate mass products of a fission event are two large fission fragments, which are remnants of the formed U-236 nucleus. These fragments emit, on average, two or three free neutrons (in average 2.47), called "prompt" neutrons. A subsequent fission fragment occasionally undergoes a stage of radioactive decay (which is a beta minus decay
) that yields a new nucleus (the emitter nucleus) in an excited state that emits an additional neutron, called a "delayed" neutron, to get to ground state. These neutron-emitting fission fragments are called delayed neutron precursor atoms.

Delayed Neutron Data for Thermal Fission in U-235[1][2]

Group Half-Life (s) Decay Constant (s−1) Energy (keV) Yield, Neutrons per Fission Fraction
1 55.72 0.0124 250 0.00052 0.000215
2 22.72 0.0305 560 0.00346 0.001424
3 6.22 0.111 405 0.00310 0.001274
4 2.30 0.301 450 0.00624 0.002568
5 0.610 1.14 - 0.00182 0.000748
6 0.230 3.01 - 0.00066 0.000273

Importance in nuclear reactors

If a

resonance absorptions
of neutrons, that usually tend to decrease the reactor's reactivity when temperature rises; but the reactor would run the risk of being damaged or destroyed by heat.

However, thanks to the delayed neutrons, it is possible to leave the reactor in a

subcritical state as far as only prompt neutrons are concerned: the delayed neutrons come a moment later, just in time to sustain the chain reaction when it is going to die out. In that regime, neutron production overall still grows exponentially, but on a time scale that is governed by the delayed neutron production, which is slow enough to be controlled (just as an otherwise unstable bicycle can be balanced because human reflexes are quick enough on the time scale of its instability). Thus, by widening the margins of non-operation and supercriticality and allowing more time to regulate the reactor, the delayed neutrons are essential to inherent reactor safety
, even in reactors requiring active control.

The lower percentage[3] of delayed neutrons makes the use of large percentages of plutonium in nuclear reactors more challenging.

Fraction definitions

The precursor yield fraction β is defined as:

and it is equal to 0.0064 for U-235.

The delayed neutron fraction (DNF) is defined as:

These two factors, β and DNF, are almost the same thing, but not quite; they differ in the case a rapid (faster than the decay time of the precursor atoms) change in the number of neutrons in the reactor.

Another concept, is the effective fraction of delayed neutrons βeff, which is the fraction of delayed neutrons weighted (over space, energy, and angle) on the adjoint neutron flux. This concept arises because delayed neutrons are emitted with an energy spectrum more thermalized relative to prompt neutrons. For low enriched uranium fuel working on a thermal neutron spectrum, the difference between the average and effective delayed neutron fractions can reach 50 pcm.[4]

See also

References

  1. ^ J. R. Lamarsh, Introduction to Nuclear Engineering, Addison-Wesley, 2nd Edition, 1983, page 76.
  2. ^ G. R. Keepin, Physics of Nuclear Kinetics, Addison-Wesley, 1965.
  3. ^ "Nuclear Data for Safeguards".
  4. OSTI 991100. {{cite journal}}: Cite journal requires |journal= (help
    )

External links