발행물

논문
컨퍼런스

전체 논문

115

101

Blankets for tritium catalyzed deuterium (TCD) fusion reactors
Jiyoung Jung, E. Greenspan, George H. Miley
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information), 1984

102

Assessments of Tritium Breeding Requirements and Breeding Potential for the STARFIRE/Demo Design
Jiyoung Jung, M. Abdou
Nuclear Technology - Fusion, 1983

103

Tokamak fusion reactors with less than full tritium breeding
K. Jr. Evans, J.G. Gilligan, Jiyoung Jung
1983

104

Waste Management of First Wall and Blanket Structural Materials for Tokamak Fusion Reactors
S. Vogler, M.J. Steindler, Jiyoung Jung
Nuclear Technology - Fusion, 1983

105

The Effective Cost of Tritium for Tokamak Fusion Power Reactors with Reduced Tritium Production Systems
J.G. Gilligan, K. Evans, Jiyoung Jung
Nuclear Technology - Fusion, 1983

106

An analysis of activation and the impact of tritium breeding media and structural materials for a commercial tokamak fusion reactor design
Jiyoung Jung
Nuclear Technology, 1983

107

Impact of fusion reactor activation on materials recycling for starfire
Jiyoung Jung
Transactions of the American Nuclear Society, 1982

108

STARFIRE, a commercial tokamak power plant design
C.C. Baker, Mohamed Abdou, C. D. Boley, A.E. Bolon, J.N. Brooks, R.G. Clemmer, D.A. Ehst, K. Evans, P.A. Finn, R. Fuja, Y. Gohar, Jiyoung Jung, W.J. Kann, R.F. Mattas, Β. N. Misra, H. L. Schreyer, Dale Smith, H. Stevens, L.R. Turner, D.A. De Freece, C.F. Dillow, G.D. Morgan, C.A. Trachsel, D. Graumann, J. Alcorn, R.E. Fields, R. Prater, J. Kokoszenski, Kevin M. Barry, Michael Cherry, H.W. Klumpe, R.W. Conn, G.A. Emmert, I.N. Sviatoslavsky, D.K. Sze
Nuclear Engineering and Design, 1981

109

Interpolation method for the transport theory and its application in fusion-neutronics analysis
Jiyoung Jung
1981

110

Importance of shield design in minimizing radioactive-material inventory in tokamaks
Jiyoung Jung, M. Abdou
1980