The Beryllium emitted 30 neutrons per 10^6 alpha particles.

Article may give you some idea

http://www.sbfisica.org.br/bjp/files/v35_797.pdf

it is possible to measure neutron flux by using some methods.

absolute methods using : Manganese Bath (http://www.npl.co.uk/science-technology/neutron-metrology/research/manganese-bath) or by using neutron foil activation ().https://ojs.ujf.cas.cz/~wagner/transmutace/studentpraxe/stevenreferat.pdf

the best method for dose rate determination for any neutron source are bonner sphere spectrometer.

Maybe this publication is also of some help.

I just googled Am-Be neutron sources

http://web.ornl.gov/~webworks/cppr/y2001/rpt/117954.pdf

Dear Manoj,

Depending on your objectives you can make several approximations to simulate the Am-Be source. The reference source is described by ISO 8529.

You may also look at ORNL/TM-2003/184 doc to see for some hint.

Regards, Hope it helps.

Darius

I agree with professor Mohamed Fayez-Hassan

Thank you very much for this valuable information

https://www.nrc.gov/docs/ML1122/ML11229A704.pdf

Neutron spectra is complex with average 4-5Mev; neat spikes at 4.7, 6.5 & 8 Mev.

Neutron flux can be calculated from the known yield of 80n/10exp6 Bq .

you can use many Monte Carlo codes like fluka, Geant4, MCNPX, MCNP5, MCNP,

this will give you an estimation about the neutron energy distribution and the average neutron energy via neutron transport phenomena

you can use many Monte Carlo codes like fluka, Geant4, MCNPX, MCNP5, MCNP,

this will give you an estimation about the neutron energy distribution and the average neutron energy via neutron transport phenomena