The Source Permeator System and Tritium Transport in the TEX PbLi Loop
Journal Article
·
· Fusion Science and Technology
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
In this work, permeation is investigated for the introduction of hydrogen isotopes into PbLi for the Tritium Extraction eXperiment (TEX). TEX is a forced-convection PbLi loop under construction at Idaho National Laboratory (INL) that will test the vacuum permeator (VP) method of tritium extraction from PbLi. The source permeator (SP) delivers atomic hydrogen (H, D, and T) from a gas-phase reservoir into the PbLi via a permeable dense metal membrane. A modular and a fixed source permeator system are presented. In the modular design, PbLi flows through the inside of a tubular membrane and gas-phase hydrogen is introduced on the outside of the membrane. Atomic hydrogen permeates radially inward through the membrane into the PbLi. In the fixed design, PbLi flows into an expansion chamber with closed-ended tubular membranes inserted. Gas-phase hydrogen is introduced on the inside of the closed-ended membranes and atomic hydrogen permeates radially outward into the flowing PbLi. Hydrogen-transport models based on steady-state mass transport through PbLi and permeation through the metal membrane were developed to assess the operation of the source permeator relative to experimental variables and to allow understanding of uncertain parameter effects, such as PbLi hydrogen-transport properties and the effective hydrogen permeability of the vacuum permeator. This modeling effort considers iron as the source permeator material and vanadium as the vacuum permeator material.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES)
- Grant/Contract Number:
- AC05-00OR22725; AC07-05ID14517
- OSTI ID:
- 1902989
- Alternate ID(s):
- OSTI ID: 1907218
- Report Number(s):
- INL/JOU-21-65446-Rev000
- Journal Information:
- Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: - Vol. -; ISSN 1536-1055
- Publisher:
- American Nuclear SocietyCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Similar Records
SOFE2023 Presentation: "Tritium Safety and Sensitivity Analysis of Tritium Extraction eXperiment (TEX) PbLi Loop Using MELCOR-TMAP"
Parametric Study of the Vacuum Permeator for the Tritium Extraction eXperiment
Conference
·
Tue Jul 25 20:00:00 EDT 2023
·
OSTI ID:1994265
Parametric Study of the Vacuum Permeator for the Tritium Extraction eXperiment
Journal Article
·
Mon May 22 20:00:00 EDT 2023
· Fusion Science and Technology
·
OSTI ID:1987842