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in creator/contributor: "Causey, R. A."

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Silver transport in H-451 graphite

Diffusion profiles have been measured for silver in hollow and solid cylinders in the temperature range 490 to 800/sup 0/C. The profiles show two components of diffusion. There is a high concentration, relatively immobile zone near the surface and a low concentration, rapidly moving component deeper into the sample. The rapid component is well fitted by the diffusion equation when irreversible trapping is assumed. The diffusion coefficients determined by least-square analysis of the profiles ca… more

Date: January 1, 1981

Creator: Causey, R. A. & Wichner, R. P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Proceedings of the 4th International Workshop on Tritium Effects in Plasma Facing Components

The 4th International Workshop on Tritium Effects in Plasma Facing Components was held in Santa Fe, New Mexico on May 14-15, 1998. This workshop occurs every two years, and has previously been held in Livermore/California, Nagoya/Japan, and the JRC-Ispra Site in Italy. The purpose of the workshop is to gather researchers involved in the topic of tritium migration, retention, and recycling in materials used to line magnetic fusion reactor walls and provide a forum for presentation and discussion… more

Date: February 1, 1999

Creator: Causey, R. A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Influence of lattice damage on retention and transport of deuterium in beta silicon carbide

Experiments were done to determine effect of lattice damage on solubility and transport of deuterium (D) in silicon carbide. Beta SiC samples were irradiated with energetic ions to produce lattice damage, and were then soaked in D{sub 2} gas at 1000C. Concentration of D versus depth was then measured by nuclear reaction analysis. Very near the surface (<0.5{mu}m), concentration of D was larger in irradiated than in unirradiated, but beyond 1 {mu}m the D concentrations were similar ({approximate… more

Date: October 1, 1993

Creator: Wampler, W. R. & Causey, R. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

The effect of production temperature on the retention of tritium in vapor deposited beta silicon carbide

This is the final report in the prematurely terminated research program on the behavior of tritium in the NPR-MHTGR tritium target materials. This report addresses effect of production temperature of the silicon carbide layer on tritium permeation characteristics of the silicon carbide. Equilibrium tritium retention measurements performed using samples vapor deposited at 1400 and 1700C were compared to earlier results for samples deposited at 1550C. The tritium retention characteristics of the … more

Date: October 1, 1993

Creator: Causey, R. A.; Wampler, W. R. & Kaae, J. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Using the Tritium Plasma Experiment to evaluate ITER PFC safety

The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capability of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 {times} 10{sup 19} ions/cm{sup 2} {center_dot} s and a plasma temperature of about 15 eV using a plasma that includes tritium. With the closure of the Tritium Research Laborator… more

Date: July 1, 1993

Creator: Longhurst, G. R.; Anderl, R. A.; Bartlit, J. R.; Causey, R. A. & Haines, J. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Erosion and Redeposition Experiments in the PISCES Facility

The modification of surfaces during exposure to plasma bombardment is a critical issue in the development of limiter and wall materials for fusion confinement experiments. Controlled studies of the erosion and redeposition of materials during high flux and fluence plasma exposure are now possible in the PISCES facility. PISCES is a continuously operating plasma device which has achieved hydrogen plasma densities of over 10/sup 13/ cm/sup -3/ and electron temperatures of 5 to 24 eV over large ar… more

Date: May 1, 1986

Creator: Goebel, D. M.; Hirooka, Y.; Conn, R. W.; Leung, W. K.; Campbell, G. A.; Bohdansky, J. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Materials surface modification by plasma bombardment under simultaneous erosion and redeposition conditions

The first in-depth investigation of surface modification of materials by continuous, high-flux argon plasma bombardment under simultaneous erosion and redeposition conditions have been carried out for copper and 304 stainless steel using the PISCES facility. The plasma bombardment conditions are: incident ion flux range from 10/sup 17/ to 10/sup 19/ ions sec/sup -1/cm/sup -2/, total ion fluence is controlled between 10/sup 19/ and 10/sup 22/ ions cm/sup -2/, electron temperature range from 5 to… more

Date: July 1, 1986

Creator: Hirooka, Y.; Goebel, D. M.; Conn, R. W.; Campbell, G. A.; Leung, W. K.; Wilson, K. L. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Studies of tritiated co-deposited layers in TFTR

Plasma facing components in TFTR contain an important record of plasma wall interactions in reactor grade DT plasmas. Tiles, flakes, wall coupons and dust samples have been retrieved from the TFTR vessel for analysis. Selected samples have been baked to release tritium and assay the tritium content. The in-vessel tritium inventory is estimated to be 0.5 g and is consistent with the in-vessel tritium inventory derived from the difference between tritium fueling and tritium exhaust. Relatively hi… more

Date: May 30, 2000

Creator: Skinner, C. H.; Gentile, C. A.; Ascione, G.; Causey, R. A.; Hayaski, T.; Hogan, J. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Gas retention in irradiated beryllium

Helium (an inert gas) with low solubility in beryllium is trapped in irradiated beryllium at low temperatures (<100{degree}C) while the tritium generated may have some mobility and be released. The subject of tritium retention in irradiated beryllium within fusion reactor blankets is of considerable interest in their conceptual design. Results from experiments on three sets of irradiated beryllium specimens are examined in this paper. The beryllium specimens were irradiated at abut 75{degree}C … more

Date: June 1, 1990

Creator: Beeston, J. M.; Miller, L. G.; Longhurst, G. R. (EG and G Idaho, Inc., Idaho Falls, ID (USA)) & Causey, R. A. (Sandia National Labs., Albuquerque, NM (USA))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Studies of tritiated co-deposited layers in TFTR

Plasma facing components in TFTR contain an important record of plasma wall interactions in reactor grade DT plasmas. Tiles, flakes, wall coupons, a stainless steel shutter and dust samples have been retrieved from the TFTR vessel for analysis. Selected samples have been baked to release tritium and assay the tritium content. The in-vessel tritium inventory is estimated to be 0.56 g and is consistent with the in-vessel tritium inventory derived from the difference between tritium fueling and tr… more

Date: June 28, 2000

Creator: Skinner, C. H.; Gentile, C. A.; Ascione, G.; Carpe, A.; Causey, R. A.; Hayashi, T. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Studies of tritiated co-deposited Layers in TFTR

Date: May 22, 2000

Creator: Skinner, C. H.; Gentile, C. A.; Ascione, G.; Carpe, A.; Causey, R. A.; Hayashi, T. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Using the Tritium Plasma Experiment to evaluate ITER PFC safety. [Plasma-Facing Components]

The Tritium Plasma Experiment was assembled at Sandia National Laboratories, Livermore to investigate interactions between dense plasmas at low energies and plasma-facing component materials. This apparatus has the unique capability of replicating plasma conditions in a tokamak divertor with particle flux densities of 2 [times] 10[sup 19] ions/cm[sup 2] [center dot] s and a plasma temperature of about 15 eV using a plasma that includes tritium. With the closure of the Tritium Research Laborator… more

Date: January 1, 1993

Creator: Longhurst, G. R.; Anderl, R. A. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Bartlit, J. R. (Los Alamos National Lab., NM (United States)); Causey, R. A. (Sandia National Labs., Livermore, CA (United States)) & Haines, J. R. (MDC Aerospace, St. Louis, MO (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department