Development of a Thermochemical Database for Sodium Fast Reactor Mechanistic Source Term Calculations
Conference
·
OSTI ID:1785319
An accurate assessment of the radionuclide source term for sodium fast reactors requires a predictive understanding of the chemical speciation and phase transformations of key dose contributing radionuclides, including those released to the sodium pool and cover gas region. Developing models for chemical speciation and phase equilibria requires the compilation of thermodynamic constants and experimentally determined functions that account for non-ideal solution behavior. For the present study, a thermochemical database, including parameters accounting for non-ideal chemical mixing, was compiled and used for a set of mechanistic source term trial calculations for a metal-fueled, pool-type sodium fast reactor [1].
- Research Organization:
- Argonne National Laboratory (ANL)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1785319
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermochemical Modeling of Radionuclide Vapor-Liquid Equilibria in Sodium Pools for SFR Mechanistic Source Term Analysis
Regulatory Technology Development Plan - Sodium Fast Reactor: Mechanistic Source Term – Trial Calculation
An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor
Conference
·
Sat Jun 01 00:00:00 EDT 2024
·
OSTI ID:2361027
Regulatory Technology Development Plan - Sodium Fast Reactor: Mechanistic Source Term – Trial Calculation
Technical Report
·
Sat Oct 01 00:00:00 EDT 2016
·
OSTI ID:1334189
An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor
Conference
·
Mon Jun 26 00:00:00 EDT 2017
·
OSTI ID:1389837