Decay Source Spectra in ORIGEN for MAVRIC

[A. Hargreaves]

Hello folks!

I'm trying to decay the isotopics of a waste stream (consisting of various activation and fission products) in ORIGEN then use the distribution block to transition this stream into my source distribution for use in MAVRIC but it keeps erroring out with this as it's final log in the MAVRIC .out file:

Spectral data:

1. total neutron spectrum (neutron/s) no data

2. spontaneous fission (neutron/s) no data

3. (alpha,n) spectrum (neutron/s)no data

4. delayed n spectrum (neutron/s)no data

5. photons (photon/s)

My distribution block is as follows:

distribution 11

title="photon"

special="origensBinaryConcentrationFile"

filename="[PATH]"

parameters 2 2 end

end distribution

I'm wondering what it causing this and if I'm not calling the .f71 properly? Or if I just am misunderstanding what functionality SCALE has to do this kind of thing?

Thank you!

[Pavlo Ivanusa]

It looks like your F71 file only has photon on it, but you're trying to read spontaneous fission data. If you need the neutron data, you'll have to go back to your ORIGEN runs to make sure you're saving it properly. If you only need the photon source, then change your parameters line to "parameters 2 5".

[David Holler]

Hi Pavlo,

When using an ORIGEN file for a source in MAVRIC, is there a way to see the contributions of each isotope to a point detector dose?

[Pavlo Ivanusa]

I don't think there is an easy way of doing so in MAVRIC. I would probably go with two options:

1. Have separate cases for your nuclides of interest in ORIGEN and then create the F71 file for those to read into MAVRIC.

2. Run MAVRIC with distributions using the "origensDiscreteGammas" special parameter. 

I'd be happy to be corrected, but those are the two easiest options I see.