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.
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.
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...
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...
