Absorbed Radioactivity: Safe Handling of Irradiated Metals

  • Thread starter Thread starter Busybee
  • Start date Start date
  • Tags Tags
    Radioactivity
Click For Summary
SUMMARY

The discussion centers on the safety handling of irradiated metals, specifically addressing the potential for residual radioactivity after exposure to radiation. It is established that materials irradiated by gamma, beta, or alpha radiation do not exhibit stray radiation unless high-energy interactions occur. In contrast, neutron irradiation can induce residual radioactivity due to the activation of stable nuclides into radionuclides. The importance of using a sample holder with a low neutron absorption cross-section is emphasized when irradiation occurs in a neutron field.

PREREQUISITES
  • Understanding of radiation types: gamma, beta, alpha, and neutron radiation
  • Knowledge of radiation dose measurement (rad/hr and total integrated dose)
  • Familiarity with nuclear interactions and isotope changes
  • Concept of neutron absorption cross-section in materials
NEXT STEPS
  • Research the effects of neutron irradiation on various metals
  • Study the principles of radiation safety and handling irradiated materials
  • Learn about the decay rates of common radionuclides produced from neutron activation
  • Investigate materials with low neutron absorption cross-sections for sample holders
USEFUL FOR

Radiation safety officers, nuclear engineers, researchers in materials science, and anyone involved in the handling and processing of irradiated metals.

Busybee
Messages
1
Reaction score
0
I need some source material to understand if, the metals which are gone through irradiation process, can exhibit radiation.
Though we will be irradiating at a dose rate of ≈ 1M rad/hr, Our Total Integrated dose requirement is 55M rad. The question I have is for the material used to hold the sample are metallic and we do not want the handlers to get exposed to stray radiation after the test.
 
Engineering news on Phys.org
Busybee said:
I need some source material to understand if, the metals which are gone through irradiation process, can exhibit radiation.
Though we will be irradiating at a dose rate of ≈ 1M rad/hr, Our Total Integrated dose requirement is 55M rad. The question I have is for the material used to hold the sample are metallic and we do not want the handlers to get exposed to stray radiation after the test.
There is no stray radiation after a material is irradiated by gamma, beta or alpha radiation, unless the energy is sufficiently high to cause a nuclear interaction (change of isotope). Neutron irradiation, in which neutrons are absorbed by stable nuclides, does induce residual radioactivity when the activation of material results in radionuclides.

What type of radiation will one use to irradiate the target? Will the irradiation take place in a reactor core (i.e., neutron field)? If so, then one will want to use a sample holder with a low neutron absorption cross-section.

Otherwise, one would have to determine the amount of material activated, then wait for the radionuclides to decay until radiation levels are below limits.
 

Similar threads

Replies
1
Views
2K
  • · Replies 9 ·
Replies
9
Views
5K
  • · Replies 13 ·
Replies
13
Views
3K
  • · Replies 6 ·
Replies
6
Views
4K
  • · Replies 28 ·
Replies
28
Views
3K
  • · Replies 33 ·
2
Replies
33
Views
8K
  • · Replies 10 ·
Replies
10
Views
3K
  • · Replies 1 ·
Replies
1
Views
2K
  • · Replies 36 ·
2
Replies
36
Views
6K
  • · Replies 7 ·
Replies
7
Views
5K