4-7 November 2019
PSI Auditorium
Europe/Zurich timezone
Presentation slides are available now (select Timetable)

Recent Development of Thermochimica for Simulations of Nuclear Materials

5 Nov 2019, 09:20
20m
WHGA/001 (PSI Auditorium)

WHGA/001

PSI Auditorium

Forschungstrasse 11 5232 Villigen PSI Switzerland

Speaker

Max Poschmann (University of Ontario Institute of Technology)

Description

The open-source equilibrium thermochemistry library Thermochimica has previously been employed to study uranium dioxide nuclear fuel for light-water reactor applications. Recently, significant improvements to the efficiency and range of applications of Thermochimica have been made. We will discuss these advances and demonstrate applications of Thermochimica for next-generation nuclear technologies, such as Molten Salt Reactors (MSRs) and Tristructural-isotropic (TRISO) fuels. Calculations on popular molten salt fuel materials, such as FliNaK, FliBe and fission product containing salts, have been enabled through the implementation of the quadruplet approximation to the modified quasichemical model in Thermochimica, which takes into account first and second-nearest-neighbor short-range ordering contributions to the Gibbs energies of liquid solution phases. Coupling of Thermochimica to various other software packages, such as the Multiphysics Object Oriented Simulation Environment (MOOSE), Coolant-Boiling in Rod Arrays - Two Fluids(CTF), Virtual Environment for Reactor Applications (VERA), and Oak Ridge Isotope GENeration (ORIGEN) for nuclear fuel applications will also be demonstrated.

Primary author

Max Poschmann (University of Ontario Institute of Technology)

Co-authors

Dr Bernard Fitzpatrick (University of Ontario Institute of Technology) Dr Srdjan Simunovic (Oak Ridge National Lab) Dr Markus Piro (University of Ontario Institute of Technology)

Presentation Materials