[ RadSafe ] Tritium production in a nuke plant

[Rahim Ghanooni]

John:

Thanks for the suggestion, yes we have GALE and used it.  This is the
problem with GALE.

GALE is designed for a typical 600 to 800 MWt PWR, or BWR.  We are
designing a modular reactor 45 MW, and we do not have many of the systems
that other nukes have (WWW. NUSCALEPOWER.com).

I manually calculated the radionuclide inventory in the reactor coolant and
the steam generator, using nureg-0017, then creating a spreadsheet
determining the gaseous and liquid effluent.  NRC requires to calculate
C-14, Ar-41, and T.  The first two are calculated, and I am trying to get
more information on T.  I also calculated the fuel depletion, and by the
time I finish determining the T activity, I am done with the source term,
then start shielding calculation and dose assessment.

Rahim


On Thu, Apr 18, 2013 at 8:29 AM, <JOHN.RICH at sargentlundy.com> wrote:

> Rahim
>
> You probably haven't used the "GALE" codes (NUREG-0016 and NUREG-0017) for
> a long time.  They address tritium production and release.  They're a
> little old but they were NRC approved.  It might be worth considering
> using these codes again if nothing more current meets your needs.
>
>  - -jmr
>
>
> John Rich
> 312-269-3768
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