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J.H. Westsik

Annual report on the characteristics of high-level waste glasses
1977 · J Mendel, W Ross, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 68
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Time and Temperature Dependence of the Leaching of a Simulated High-Level Waste Glass
1981 · J. H. Westsik, R. D. Peters · Springer eBooks · 29
Water migration through compacted bentonite backfills for containment of high-level nuclear waste
1983 · J.H. Westsik, F.N. Hodges, et al. · Nuclear and Chemical Waste Management · 20
Permeability, Swelling and Radionuclide Retardation Properties of Candidate Backfill Materials
1981 · J. H. Westsik, L. A. Bray, et al. · MRS Proceedings · 17
Closed Fuel Cycle Waste Treatment Strategy
2015 · J. Vienna, USDOE Office of Nuclear Energy (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 13
In situ vitrification: Test results for a contaminated soil-melting process
1989 · J Buelt, C Timmerman, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 11
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Temperature Dependence for Hydrothermal Reactions of Waste Glasses and Ceramics
1980 · J. H. Westsik, J. W. Shade, et al. · Advances in nuclear science and technology · 8
Materials Characterization Center workshop on leaching of radioactive waste forms. Summary report
1980 · W.A. Ross, D.M. Strachan, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7
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High-temperature leaching of an actinide-bearing, simulated high-level waste glass
1983 · J.H. Jr. Westsik, C.O. Harvey, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 6
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Hydrothermal Glass Reactions in Salt Brine
1979 · J. H. Westsik, R. P. Turcotte · Springer eBooks · 6
Development of backfill material as an engineered barrier in the waste package system- Interim topical report
1981 · E.J. Wheelwright, F.N. Hodges, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
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Summary of Molten-salt Breeder Reactor Design Studies.
1968 · P.R. Kasten, E.S. Bettis, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
Comparative assessment of TRU waste forms and processes. Volume I. Waste form and process evaluations
1982 · W.A. Ross, R.O. Lokken, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
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A Comparative Assessment of Tru Waste Forms and Immobilization Processes
1981 · W. A. Ross, C. O. Harvey, et al. · MRS Proceedings · 3
Temperature control system for liquid-fed ceramic melters
1986 · J.H. Jr. Westsik · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
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Comparison of 200 Liter and 40 Milliliter Leach Tests
1982 · J. H. Westsik, C. O. Harvey, et al. · MRS Proceedings · 2
Thermal and radiation effects on borosilicate waste glasses. [For incorporation of radioactive wastes]
1976 · J.E. Mendel, W.A. Ross, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
Melter viewing system for liquid-fed ceramic melters
1988 · J.H. Jr. Westsik, B.B. Brenden · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
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Instrumentation for remote monitoring and control of liquid-fed ceramic melters
1985 · J.H. Jr. Westsik, B.M. Wise, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Instrumentation concepts for nuclear waste glass melters
1985 · Steven Barnes, Barry M. Wise, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Leaching test methods for waste forms
1980 · J.E. Mendel, R.P. Turcotte, et al. · Transactions of the American Nuclear Society · 1
A combined cycle for solar-fossil hybrid power generation
1979 · E. Y. Lam, J.H. Westsik · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
Chemical durability of zinc borosilicate nuclear waste glass
1977 · J.H. Westsik, J.E. Mendel · University of North Texas Digital Library (University of North Texas) · 1
Addendum to ORNL CF-61-2-46, Molten-Salt Reactor Experiment Preliminary Hazards Report
1961 · S. E. Beall, R. B. Briggs, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1
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TFA Tanks Focus Area Multiyear Program Plan FY00-FY04
1999 · BA Carteret, JH Westsik, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 42
Citation count: 214
H-index: 7
I10-index: 6
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