Dose of radiation from the neutron source

AI Thread Summary
The discussion focuses on calculating the absorbed dose of radiation from a Cf-252 neutron source, given its activity, distance, and protective shielding. Key steps include determining the energy loss of neutrons as they pass through a 30 cm water-based shield and assessing the remaining energy to calculate the absorbed dose for an 80 kg individual. Participants suggest that understanding neutron interactions with materials is crucial for accurate dose calculations. Additionally, there is a query about appropriate resources for further reading on radiation dose calculations and whether to seek advice in specialized physics forums. The conversation emphasizes the importance of both theoretical understanding and practical application in radiation safety.
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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