Dose of radiation from the neutron source

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SUMMARY

The discussion focuses on calculating the absorbed dose of radiation from a Cf-252 neutron source with an activity of 200 kBq, considering a 30 cm water-based protective shield. Key calculations involve determining the energy loss of neutrons as they pass through the protection and the subsequent absorbed dose for an 80 kg individual at a distance of 1 meter from the source. The participants emphasize the importance of understanding neutron attenuation and energy reduction through shielding to accurately assess radiation exposure.

PREREQUISITES
  • Understanding of neutron radiation and its properties
  • Knowledge of radiation shielding concepts, specifically water-based materials
  • Familiarity with dose calculation methods in radiation physics
  • Basic principles of radioactivity and decay, particularly related to Cf-252
NEXT STEPS
  • Research neutron attenuation coefficients for various materials
  • Learn about the calculation of absorbed dose using the formula: Dose = Energy Absorbed / Mass
  • Explore the use of Monte Carlo simulations for radiation transport and dose estimation
  • Study the principles of radiation protection and safety standards in nuclear physics
USEFUL FOR

Radiation physicists, health physicists, nuclear engineers, and anyone involved in radiation safety and dose assessment from neutron sources.

DB51
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Hi All. Could you help me with following:

Homework Statement
We have:

Neutron source Cf-252

Activity of Neutron source Cf-252 = 200 kBq

The thickness of the protection of water-based = 30 cm

Weight of the man = 80 kg

Distance to a source = 1 m

Questions

How to calculate the absorbed dose for this men,if we know only activity of Cf-252, distance to a source, thickness of protection and weight of man.

How to calculate the absorbed dose from neutron source for human body? With shield and without.

If I correctly understand:

1) at first it is necessary to calculate how many energies lose neutrons transiting through protection. Whether all neutrons are decelerated transiting through protection.

2)Then, when will be known, what energy have neutrons after passage through protection, is possible to start to consider the absorbed doseCould you help me with this problem and could me advise where i can read about how to calculate radiation dose from neutron source.
 
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Maybe I should ask my question in High Energy, Nuclear, Particle Physics section ??
 

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