|Message: Re: Cf 252 Neutron Source||Not Logged In (login)|
Click on the Forum title, e.g. on the "Forums by Category" page, to read a sequence of postings to the Forum and its threads all in one page. If you are only interested in one thread or the thread following a specific posting, click the thread or the posting, which takes you to a smaller page, which contains only the part you are interested in and may be easier to navigate.
Messages are "chained" if there are only replies at the first level, i.e. 1/1.html, 1/1/1.html etc. In case of "chained" messages the message number is replaced by the icon and there is no indentation.
Inline: Display the subject line only or also the text of the posting(s); for the choice "All" the "Outline" choices are switched off.
|1||0||1||no text / full text of posting|
|2||1||All||text for level 1 only / text for All postings|
Outline: Choose the depth of the posting thread, successive toggle controls provide increasing detail.
|1||2||1||2 levels / 1 level (original posting)|
|2||3||2||3 levels / 2 levels|
|3||3||All||3 levels / all levels (all postings)|
Unless you are explicitly studying the physics and all daughter particles of Cf-252 decay (in which case the use of G4RadioactiveDecay as Michael suggests would be appropriate), I would suggest that you use the G4GeneralParticleSource module provided with Geant4. This module provides for the construction of a wide variety of particle sources, including very complex ones. See the user manual at: http://reat.space.qinetiq.com/gps/new_gps_sum_files/gps_sum.htm
Without knowing your specific requirements, my guess is that you require a point Cf-252 spontaneous neutron fission source (isotropic angle, correct fission energy spectrum). I have attached a macro file that models exactly this neutron source (note that G4GeneralParticleSource is controlled via runtime commands so you'll need to execute this macro from within your simulation, e.g.:
As always, the usual warnings apply. Please verify that the attached macro file produces the neutron spectrum that you require.
Hope this helps.
|Inline Depth:||Outline Depth:||Add message:|