I have to do a burnup simulation of fuel in a pool-type research reactor.
But I only have cross section sets for BWR and PWR.
In your opinion which one of the two available cross section sets fit the best for the pool-type reactor and why ?
Thanks.
Yes, it is "a/o".
Searching on the internet I found that "a/o" means "total atom per cent". A colleague of mine told me that "a/o" corresponds to what is called "%FIMA", that is, "fissions per initial metal atom": the percentage of atoms of heavy metal having undergone fission. This includes...
In old publications from the 80's and 90's I find the burn-up expressed in "a/o".
For example it reads that a certain fuel rod has reached a burn-up of 6.2 a/o.
What does it mean ? How can I convert this a/o in MWd/kg HM ?
Thanks in advance.
Thank you very much, PNachtwey.
Could you retry setting a = nT, with n equal to any integer (for example n = 3) ?
I've read some literature and found many examples of continuous systems preceded by a signal-discretizing S&H: because of the upstream S&H the z-transform should be employed.
But I...
I have a continuous system, having L-transfer function F(s)G(s), followed by a sample-and-hold, according to the following scheme:
Input signal -> F(s) --> G(s) --> S&H(period = T) -> Output signal
The sample-and-hold samples its input signal at times t = nT (so T is the period).
I have...
racookpe1978, EnergyMix,
thank you very much for your help.
I have been given a sheet reporting an example of nuclide vector contained in a cask. But it's just an example.
There are the following nuclides: H-3, C-14, Mn-54, Fe-55, Co-60, Ni-63, Ag-110m, Sb-125, I-129, Cs-134, Cs-137, Pu-241...
I don't have the nuclide vector yet, because now I'm not yet asked to make the shielding calculation, but only to forecast how many working hours I need to do it. On the basis of my forecast my employer would make an offer to the client.
The only information I dispose of now is that it's...
I have to make a shielding calculation of some radioactive scrap metal in a cask, using Geant4 (hence Monte-Carlo).
I will be given a nuclide vector and I'll have to calculate the ambient dose equivalent rate outside of the cask.
The nuclide vector I will be given will be something like:
Co60...
