Do you know if there is a similar database with stopping power and range tables for neutrons just like there are for electrons, protons and alphas respectively
http://physics.nist.gov/PhysRefData/Star/Text/ASTAR.html
http://physics.nist.gov/PhysRefData/Star/Text/PSTAR.html
http://physics.nist.gov/PhysRefData/Star/Text/ESTAR.html
I wish to moderate neutrons from a Am/Be source to thermal neutrons and wish to calculate the amount/thickness of water I would require to slow them down.
Help would be greatly appreciated.
Cheers,
Shri
This presentation may be helpful for your calculations:
https://www.nrc.gov/docs/ML1122/ML11229A721.pdf
You can find the cross sections in ENDF at the Brookhaven national nuclear data center.:
https://www.nndc.bnl.gov
or you can use the european version JANIS (works on you computer if you have JRE)
https://www.oecd-nea.org/janis/
There are no stopping powers for neutrons, as neutrons are uncharged. The stopping power is the energy loss per unit distance (cm or g/cm^2) due to the interaction of a charged particle with the electrons of the medium.
I´m also recommended find the cross sections in ENDF at the Brookhaven national nuclear data center.
The thermalization of fast neutrons from the Am-Be source mentioned in the question requires a neutron transport calculation in the used geometry and material composition. The data in the ENDF libraries have to be converted into the format of the input of the transport code. For this task a user-friendly program package PREPRO can be downloaded from the Nuclear Data Section of IAEA (and of course the ENDF libraries as well).
https://www-nds.iaea.org/public/endf/prepro/
https://www-nds.iaea.org/exfor/endf.htm
- Badges
- Science topic
- Similar topics
- Linguistics
- Composition Studies
- Publication