Development of a plasma driven permeation experiment for TPE

Buchenauer, Dean; Kolasinski, Robert; Shimada, Masa; Donovan, David; Youchison, Dennis; Merrill, Brad

doi:10.1016/j.fusengdes.2014.03.009

Title: Development of a plasma driven permeation experiment for TPE

Full Record
Other Related Research

Abstract

Experiments on retention of hydrogen isotopes (including tritium) at temperatures less than 800 ?C have been carried out in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory [1,2]. To provide a direct measurement of plasma driven permeation in plasma facing materials at temperatures reaching 1000 ?C, a new TPE membrane holder has been built to hold test specimens (=1 mm in thickness) at high temperature while measuring tritium permeating through the membrane from the plasma facing side. This measurement is accomplished by employing a carrier gas that transports the permeating tritium from the backside of the membrane to ion chambers giving a direct measurement of the plasma driven tritium permeation rate. Isolation of the membrane cooling and sweep gases from TPE’s vacuum chamber has been demonstrated by sealing tests performed up to 1000 ?C of a membrane holder design that provides easy change out of membrane specimens between tests. Simulations of the helium carrier gas which transports tritium to the ion chamber indicate a very small pressure drop (~700 Pa) with good flow uniformity (at 1000 sccm). Thermal transport simulations indicate that temperatures up to 1000 ?C are expected at the highest TPE fluxes.

Authors:

Buchenauer, Dean ^[1]; Kolasinski, Robert ^[1]; Shimada, Masa ^[2]; Donovan, David ^[1]; Youchison, Dennis ^[3]; Merrill, Brad ^[2]

Sandia National Lab. (SNL-CA), Livermore, CA (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Publication Date:: Fri Apr 18 00:00:00 EDT 2014

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1162219

Report Number(s):: INL/JOU-14-33530
Journal ID: ISSN 0920-3796; PII: S0920379614001823; TRN: US1600627

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Fusion Engineering and Design

Additional Journal Information:: Journal Volume: 89; Journal Issue: 7-8; Journal ID: ISSN 0920-3796

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Permeation; Plasma; Tritium

Citation Formats


                    Buchenauer, Dean, Kolasinski, Robert, Shimada, Masa, Donovan, David, Youchison, Dennis, and Merrill, Brad. Development of a plasma driven permeation experiment for TPE.  United States: N. p., 2014. 
Web.  doi:10.1016/j.fusengdes.2014.03.009.

Copy to clipboard


                    Buchenauer, Dean, Kolasinski, Robert, Shimada, Masa, Donovan, David, Youchison, Dennis, & Merrill, Brad. Development of a plasma driven permeation experiment for TPE.  United States.  https://doi.org/10.1016/j.fusengdes.2014.03.009

Copy to clipboard


                    Buchenauer, Dean, Kolasinski, Robert, Shimada, Masa, Donovan, David, Youchison, Dennis, and Merrill, Brad. Fri .  
"Development of a plasma driven permeation experiment for TPE".  United States.  https://doi.org/10.1016/j.fusengdes.2014.03.009.  https://www.osti.gov/servlets/purl/1162219.

Copy to clipboard


                    
@article{osti_1162219,

  title        = {Development of a plasma driven permeation experiment for TPE},

  author       = {Buchenauer, Dean and Kolasinski, Robert and Shimada, Masa and Donovan, David and Youchison, Dennis and Merrill, Brad},

  abstractNote = {Experiments on retention of hydrogen isotopes (including tritium) at temperatures less than 800 ?C have been carried out in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory [1,2]. To provide a direct measurement of plasma driven permeation in plasma facing materials at temperatures reaching 1000 ?C, a new TPE membrane holder has been built to hold test specimens (=1 mm in thickness) at high temperature while measuring tritium permeating through the membrane from the plasma facing side. This measurement is accomplished by employing a carrier gas that transports the permeating tritium from the backside of the membrane to ion chambers giving a direct measurement of the plasma driven tritium permeation rate. Isolation of the membrane cooling and sweep gases from TPE’s vacuum chamber has been demonstrated by sealing tests performed up to 1000 ?C of a membrane holder design that provides easy change out of membrane specimens between tests. Simulations of the helium carrier gas which transports tritium to the ion chamber indicate a very small pressure drop (~700 Pa) with good flow uniformity (at 1000 sccm). Thermal transport simulations indicate that temperatures up to 1000 ?C are expected at the highest TPE fluxes.},

  doi          = {10.1016/j.fusengdes.2014.03.009},

  journal      = {Fusion Engineering and Design},

  number       = 7-8,

  volume       = 89,

  place        = {United States},

  year         = {Fri Apr 18 00:00:00 EDT 2014},

  month        = {Fri Apr 18 00:00:00 EDT 2014}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.fusengdes.2014.03.009

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 6 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Gas-driven permeation of deuterium through tungsten and tungsten alloys

Journal Article Buchenauer, Dean A. ; Karnesky, Richard A. ; Fang, Zhigang Zak ; ... - Fusion Engineering and Design

Here, to address the transport and trapping of hydrogen isotopes, several permeation experiments are being pursued at both Sandia National Laboratories (deuterium gas-driven permeation) and Idaho National Laboratories (tritium gas- and plasma-driven tritium permeation). These experiments are in part a collaboration between the US and Japan to study the performance of tungsten at divertor relevant temperatures (PHENIX). Here we report on the development of a high temperature (≤1150 °C) gas-driven permeation cell and initial measurements of deuterium permeation in several types of tungsten: high purity tungsten foil, ITER-grade tungsten (grains oriented through the membrane), and dispersoid-strengthened ultra-fine grain (UFG) tungstenmore »« less
Cited by 16
https://doi.org/10.1016/j.fusengdes.2016.03.045

Full Text Available
New Conceptual Design of a Test Module Assembly for Tritium Permeation Experiment

Journal Article O'hira, S ; Luo, G -N ; Nakamura, H ; ... - Fusion Science and Technology

A new conceptual design of a tritium permeation test module assembly was developed, for simulation of tritium permeation in the real plasma facing components and validation of the models and codes for evaluation of the tritium permeation. The assembly was designed for tests using powerful ion sources, which has a capability to simulate condition relevant to that of the ITER divertor. The heat load test of the prototype module has been performed using an electron beam to verify thermal and mechanical behavior of the bonded structure and to assess its structural integrity under the cyclic heat loads. Then, the firstmore »« less
Experimental apparatus for tritium permeation studies in tritium process laboratory

Conference Okuno, K ; O'Hira, S ; Yoshida, H ; ... - Fusion Technol.; (United States)

An experimental apparatus has been developed to carry out tritium permeation experiments for candidate first-wall materials subjected to a high flux of low energy tritium ions, and installed in a glovebox. The experimental apparatus consists of five main systems; (1) a tritium ion source with energies variable from 20 to 1400 eV, (2) a main chamber system for direction an ion beam onto a heated target and for measuring various implantation-related experimental parameters by means of SIMS and AES, (3) a downstream system for measuring the permeated tritium through the target specimen by means of QMS, (4) a tritium supplymore »« less
Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE

Journal Article Sharpe, J P ; Kolasinski, R D ; Shimada, M ; ... - Journal of Nuclear Materials

The Tritium Plasma Experiment (TPE) has been used to investigate deuterium fuel retention behavior in tungsten and molybdenum– materials utilized for plasma-facing surfaces in some existing tokamak plasma devices and under consideration for future devices. Although several studies have been performed over the past several years on these metals, many issues remain unresolved, including for example blister formation mechanisms and correlation to surface conditions. In this study we expose several metal samples to deuterium ion fluences up to 1026 ions/m2 and measure retention behavior with thermal desportion spectroscopy. Fractional retention of up to 2.0×10-5 is found for W at 600more »« less
https://doi.org/10.1016/j.jnucmat.2009.01.195
Tritium Decay Helium-3 Effects in Tungsten

Conference Shimada, M. ; Merrill, B. J.

A critical challenge for long-term operation of ITER and beyond to a Demonstration reactor (DEMO) and future fusion reactor will be the development of plasma-facing components (PFCs) that demonstrate erosion resistance to steady-state/transient heat fluxes and intense neutral/ion particle fluxes under the extreme fusion nuclear environment, while at the same time minimizing in-vessel tritium inventories and permeation fluxes into the PFC’s coolant. Tritium will diffuse in bulk tungsten at elevated temperatures, and can be trapped in radiation-induced trap site (up to 1 at. % T/W) in tungsten [1,2]. Tritium decay into helium-3 may also play a major role in microstructuralmore »« less
https://doi.org/10.1016/j.nme.2016.11.006

Full Text Available

Similar Records