Comparison of the thermal stability of the codeposited carbon/hydrogen layer to that of the saturated implant layerCAUSEY, R. A; WAMPLER, W. R; WALSH, D et al.Journal of nuclear materials. 1990, Vol 176-77, pp 987-991, issn 0022-3115, 5 p.Conference Paper

Helium and hydrogen release measurements on various alloys irradiated in SINQOLIVER, B. M; DAI, Y; CAUSEY, R. A et al.Journal of nuclear materials. 2006, Vol 356, Num 1-3, pp 148-156, issn 0022-3115, 9 p.Conference Paper

Deuterium retention and release from highly irradiated annealed tungsten after exposure to a deuterium DC glow dischargeOLIVER, B. M; CAUSEY, R. A; MALOY, S. A et al.Journal of nuclear materials. 2004, Vol 329-33, pp 977-981, issn 0022-3115, 5 p., bConference Paper

Use of titanium in fusion componentsDAVIS, J. W; ULRICKSON, M. A; CAUSEY, R. A et al.Journal of nuclear materials. 1994, Vol 212-15, Num A, pp 813-817, issn 0022-3115Conference Paper

Tritium migration in vapor-deposited β-silicon carbideCAUSEY, R. A; WAMPLER, W. R; RETELLE, J. R et al.Journal of nuclear materials. 1993, Vol 203, Num 3, pp 196-205, issn 0022-3115Article

RECENT ADVANCES ON HYDROGEN RETENTION IN ITER'S PLASMA-FACING MATERIALS : BERYLLIUM, CARBON, AND TUNGSTENSKINNER, C. H; HAASZ, A. A; PISAREV, A et al.Fusion science and technology. 2008, Vol 54, Num 4, pp 891-945, 55 p.Article

The effect of UV light irradiation on the removal of tritium from the codeposited carbon-tritium layer in fusion reactorsVENHAUS, T. J; PENZHORN, R. D; CAUSEY, R. A et al.Journal of nuclear materials. 2002, Vol 302, Num 2-3, pp 224-226, issn 0022-3115Article

Tritium retention and permeation through aluminum APT tubesCOWGILL, D. F; CAUSEY, R. A.Materials characterization. 1999, Vol 43, Num 2-3, pp 169-178, issn 1044-5803Article

Fuel source isotopic tailoring and its impact on international thermonuclear experimental reactor design, operation, and safetyGOUGE, M. J; HOULBERG, W. A; ATTENBERGER, S. E et al.Fusion technology. 1995, Vol 28, Num 4, pp 1644-1650, issn 0748-1896Article

Trapping of deuterium at damage in graphiteWAMPLER, W. R; DOYLE, B. L; CAUSEY, R. A et al.Journal of nuclear materials. 1990, Vol 176-77, pp 983-986, issn 0022-3115, 4 p.Conference Paper

Deuterium retention in tungsten exposed to low-energy, high-flux clean and carbon-seeded deuterium plasmasALIMOV, V. Kh; ROTH, J; CAUSEY, R. A et al.Journal of nuclear materials. 2008, Vol 375, Num 2, pp 192-201, issn 0022-3115, 10 p.Article

Status and future of the tritium plasma experimentCAUSEY, R. A; BUCHENAUER, D; TAYLOR, D et al.Fusion technology. 1995, Vol 28, Num 3, pp 1144-1147, issn 0748-1896, 2Conference Paper

The use of silicon carbide as a tritium permeation barrierCAUSEY, R. A; WAMPLER, W. R.Journal of nuclear materials. 1995, Vol 220-22, pp 823-826, issn 0022-3115Conference Paper

Evaluation of tungsten as a plasma-facing material for steady state magnetic fusion devicesHIROOKA, Y; BOURHAM, M; BROOKS, J. N et al.Journal of nuclear materials. 1992, Vol 196-98, pp 149-158, issn 0022-3115Conference Paper

Transient release of deuterium from beryllium after plasma ion implantationHSU, W. L; CAUSEY, R. A; MILLS, B. E et al.Journal of nuclear materials. 1990, Vol 176-77, pp 218-225, issn 0022-3115, 8 p.Conference Paper

Tritium retention and migration in berylliumCAUSEY, R. A; HSU, W. L; MILLS, B. E et al.Journal of nuclear materials. 1990, Vol 176-77, pp 654-660, issn 0022-3115, 7 p.Conference Paper

Be-W alloy formation in static and divertor-plasma simulator experimentsBALDWIN, M. J; DOERNER, R. P; NISHIJIMA, D et al.Journal of nuclear materials. 2007, Vol 363-365, pp 1179-1183, issn 0022-3115, 5 p.Conference Paper

Beryllium-tungsten mixed-material interactionsDOERNER, R. P; BALDWIN, M. J; CAUSEY, R. A et al.Journal of nuclear materials. 2005, Vol 342, Num 1-3, pp 63-67, issn 0022-3115, 5 p.Article

Studies of tritiated co-deposited layers in TFTRSKINNER, C. H; GENTILE, C. A; WAMPLER, W. R et al.Journal of nuclear materials. 2001, Vol 290-93, pp 486-490, issn 0022-3115Conference Paper

Hydrogen isotope retention in beryllium for tokamak plasma-facing applicationsANDERL, R. A; CAUSEY, R. A; DAVIS, J. W et al.Journal of nuclear materials. 1999, Vol 273, Num 1, pp 1-26, issn 0022-3115Article

In-vessel tritium retention and removal in ITERFEDERICI, G; ANDERL, R. A; JACOB, W et al.Journal of nuclear materials. 1999, Vol 266-69, pp 14-29, issn 0022-3115Conference Paper

Using the tritium plasma experiment to evaluate ITER PFC safetyLONGHURST, G. R; ANDERL, R. A; BARTLIT, J. R et al.Journal of fusion energy. 1993, Vol 12, Num 1-2, pp 115-119, issn 0164-0313Conference Paper

Analysis of deuterium recycling in JET under beryllium first wall conditionsEHRENBERG, J; PHILIPPS, V; DE KOCK, L et al.Journal of nuclear materials. 1990, Vol 176-77, pp 226-230, issn 0022-3115, 5 p.Conference Paper

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