ANS / Publications / Journals / Fusion Science and Technology

Safety and Environmental Characteristics of Recent D-³He and DT Tokamak Power Reactors

G. L. Kulcinski, J. P. Blanchard, G. A. Emmert, L. A. El-Guebaly, H. Khater, C. W. Maynard, E. A. Mogahed, J. E Santarius, M. E. Sawan, I. N. Sviatoslavsky, L. J. Wittenberg

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1779-1783

Alternate Concept and Application / dx.doi.org/10.13182/FST92-A29978

Low Cost, High Yield IFE Reactors: Revisiting Velikhov's Vaporizing Blankets

B. G. Logan

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1784-1793

Alternate Concept and Application / dx.doi.org/10.13182/FST92-A29979

Magnetic Fusion for Space Propulsion

J.F. Santarius

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1794-1801

Alternate Concept and Application / dx.doi.org/10.13182/FST92-A29980

Plasma Facing Component Development: Boundary Layer Physics and Component Engineering

R. T. McGrath, A. J. Russo, R. B. Campbell, R. D. Watson

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1805-1816

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29981

Experience with Carbon Fiber Composite Limiter Tiles on TFTR

M. Ulrickson, G. Barnes, H.M. Fan, G. Labik, D. Loesser, L. Lontai, D.K. Owens

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1817-1822

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29982

Critical Issues and Innovative Solutions for the Divertor Plate Design in Future Experimental Tokamak-Type Fusion Reactors

R. Matera, W. Janssens, P. de Meester

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1823-1827

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29983

Normal Flow Heat Exchanger for Divertor Panel Cooling

Michael G. Izenson, Javier A. Valenzuela

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1828-1834

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29984

Experimental and Analytical Evaluations on Critical Heat Flux Under One Sided Heating Condition for Fusion Applications

M. Araki, M. Ogawa, M. Akiba, S. Suzuki

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1835-1839

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29985

Heat Transfer in Plasma-Facing Components of Fusion Reactors: Non-MHD Laminar Flow in Rectangular Channels

K. Takase, M. Z. Hasan, T. Kunugi

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1840-1844

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29986

A Feasibility Assessment of Liquid Metal Divertors

Chungpin Liao, Mujid S. Kazimi

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1845-1851

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29987

Performance of Graphites and Tungsten during Exposure to Pulsed Plasmas

M. A. Bourham, O. E. Hankins, J. G. Gilligan, J. D. Hurley, W. H. Eddy

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1852-1857

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29988

Thermal Cycling Experiments of Monoblock Divertor Modules for Fusion Experimental Reactors

S. Suzuki, M. Akiba, M. Araki, K. Yokoyama

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1858-1862

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29989

Sensitivity Study on Some Parameters of Disruption Erosion Analysis

T. Kunugi, M. Akiba, M. Ogawa, H. Ise, S. Yamazaki

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1863-1867

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29990

The Simulation of the Energy Deposition from Runaway Electrons in Plasma Facing Components with EGS4

T. Kunugi, M. Akiba, M. Ogawa, O. Sato, M. Nakamura

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1868-1872

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29991

High Thermal Performance CFC Divertor

R. Matera, M. Merola

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1873-1879

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29992

Thermo-Mechanical Performance of Beryllium-Coated Copper Divertors

A. E. Hechanova, M. S. Kazimi

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1880-1886

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29993

The Initial Design of First Wall for Tokamak Engineering Test Breeder

H.W. Shi, K.M. Feng, G.L. Ding, X.R. Wang, G.S. Zhang

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1887-1890

Plasma-Facing Component / dx.doi.org/10.13182/FST92-A29994

A Proposed Prototype Coil R&D Program for ITER

D. B. Montgomery

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1893-1897

Magnetic / dx.doi.org/10.13182/FST92-A29995

Comparison of Predicted and Measured Electromagnetic Data for Alcator C-MOD

R. D. Pillsbury, Jr., S. Fairfax, R. Granetz, S. Horne, I. Hutchinson, G. Tinios, S. Wolfe

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1898-1904

Magnetic / dx.doi.org/10.13182/FST92-A29996

Computational Estimates of Stress Intensity Factors for Cracks in Conductor Jackets in a Bonded Winding

K.M. Nikbin, G. A. Webster, N. Mitchell

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1905-1908

Magnetic / dx.doi.org/10.13182/FST92-A29997

A Comparison of Two Three-Dimensional Shell-Element Transient Electromagnetics Codes

J. J. Yugo, D. E. Williamson

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1909-1913

Magnetic / dx.doi.org/10.13182/FST92-A29998

Numerical Simulation of the Stability in Long Cable-in-Conduit Conductors for Fusion Magnets

C. T. Yeaw, R.L. Wong

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1914-1917

Magnetic / dx.doi.org/10.13182/FST92-A29999

Incorporation of Irradiation Effects in Design: A Review of Experience from the Breeder Reactor Program

A. Boltax

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1921-1926

Material and Tritium / dx.doi.org/10.13182/FST92-A30000

Irradiation Behavior of Bonded Structures: Impact of Swelling-Creep-Stress Relationship

M. H. Hassan, J. P. Blanchard, G. L. Kulcinski

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1927-1933

Material and Tritium / dx.doi.org/10.13182/FST92-A30001

Implantation Driven Permeation of Deuterium Through Pure Molybdenum

W.M. Shu, K. Okuno, Y. Hayashi, S. Ohira, Y. Naruse

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1934-1938

Material and Tritium / dx.doi.org/10.13182/FST92-A30002

Analysis of Tritium Transport Mechanisms at the Surface of Lithium Ceramics

Alya Badawi, A. René Raffray, Mohamed A. Abdou

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1939-1943

Material and Tritium / dx.doi.org/10.13182/FST92-A30003

Production Behavior and Its Modeling of Irradiation Defects in Lithium Oxide Under Ion Beam Irradiation

Y. Asaoka, H. Moriyama, Y. Ito

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1944-1948

Material and Tritium / dx.doi.org/10.13182/FST92-A30004

A Vacuum Disengager for Tritium Removal from HYLIFE-II Reactor Flibe

T. J. Dolan, G. R. Longhurst, E. Garcia-Otero

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1949-1954

Material and Tritium / dx.doi.org/10.13182/FST21-1949

Tritium Gas Injection System for TFTR D-T Operations

J.H. Chrzanowski, P. LaMarche, P. Ladd

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1955-1958

Material and Tritium / dx.doi.org/10.13182/FST92-A30006

Characteristics of the ‘Cryogenic-Wall’ Thermal Diffusion Column for Separation of Hydrogen Isotopes

A. Matsumoto, T. Yamanishi, K. Okuno, Y. Naruse

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1959-1963

Material and Tritium / dx.doi.org/10.13182/FST92-A30007

Sorption of Tritiated Water on Organic Materials and Subsequent Desorption

F. Ono, S. Tanaka, M. Yamawaki

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1964-1967

Material and Tritium / dx.doi.org/10.13182/FST92-A30008

Knowledge Collection and Operator Training Using an Artificial Intelligence System

J. Barnes, K. Duerre, J. Anderson, J. Bartlit, W. Parkinson, R. Sherman, T. Hayashi, Y. Naruse

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1968-1973

Material and Tritium / dx.doi.org/10.13182/FST92-A30009

Molecular Sieve Regeneration System for Assaying HTO from Detritation Systems

J. E. Nasise, J. L. Anderson, Y. Naruse

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1974-1978

Material and Tritium / dx.doi.org/10.13182/FST92-A30010

Recent Tritium Experiments of the JAERI Fuel Cleanup System (JFCU) at the Tritium Systems Test Assembly (TSTA)

T. Hayashi, S. Konishi, H. Nakamura, M. Inoue, K. Hirata, K. Okuno, Y. Naruse, J.W. Barnes, W. Harbin, R. Wilhelm, M. King, J.R. Bartlit, J.L. Anderson

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1979-1983

Material and Tritium / dx.doi.org/10.13182/FST92-A30011

Experience with Maintenance of a Tritium Contaminated Test Component at TSTA

J. Barnes, W. Harbin, J. Anderson, J. Bartlit, T. Hayashi, H. Nakamura, M. Inoue, K. Hirata, K. Okuno, Y. Naruse

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1984-1986

Material and Tritium / dx.doi.org/10.13182/FST92-A30012

Improving the Value of Risk Assessments for Fusion

D. F. Holland, L. C. Cadwallader, S. J. Piet

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1989-1993

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30013

Can We Recycle Fusion Materials?

G J Butterworth

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 1994-2000

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30014

Materials Recycling Considerations for D-T Fusion Reactors

E.T. Cheng, D.K. Sze, J.A. Sommers, O.T. Farmer III

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2001-2008

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30015

First Structural Wall Materials for Attractive Waste Management in ICF Reactors

J. Sanz, J.M. Perlado, D. Guerra, A.S. Pérez

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2009-2016

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30016

Neutron-Induced Radioactivity in a Compact Ignition Experiment

M. Zucchetti, B. Coppi

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2017-2022

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30017

Safety Analysis for “SOMBRERO”: A KrF Laser Driven IFE Reactor

H. Y. Khater, M. E. Sawan, I. N. Sviatoslavsky, L. J. Wittenberg

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2023-2028

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30018

Inertial Fusion Energy — Safety & Environmental Issues¹

S.F. Marschke, S.L. Ostrow

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2029-2035

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30019

Experiments on Exchange Flow Through Two Breaches During Loss of Vacuum Accident in Nuclear Fusion Experimental Reactor

M. Ogawa, T. Kunugi, The ITER/FER Safety Group

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2036-2040

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30020

Hydrogen/Hydrocarbon Explosions in the ITER Vacuum Vessel

P.L. Goranson

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2041-2045

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30021

A Study of the Total LOCA Transient in ITER

F. Andritsos, M. Zucchetti

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2046-2050

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30022

The Impact of Reactor Operating Time on Activation Levels for Safety Analyses

H. Y. Khater, M. E. Sawan

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2051-2055

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30023

Comprehensive Safety Evaluation Methodology for Fusion Reactor

M. Yamauchi, S. Kobayashi, Y. Seki, F. Kasahara

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2056-2061

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30024

Preliminary Decontamination and Decommissioning Plan for the Tokamak Fusion Test Reactor

G. R. Walton, J. C. Commander

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2062-2066

Safety, Recycling, and Waste Management / dx.doi.org/10.13182/FST92-A30025

Neutronics Analysis for the First Wall and Shield of the D-³He Reactor ARIES-III

M. E. Sawan, L. A. El-Guebaly

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2069-2074

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30026

European Research and Development Programme for Water-Cooled Lithium-Lead Blankets Present Status and Future Work

L. Giancarli, F. Barbier, T. Flament, M. Futterer, P. Leroy, E. Proust, J. Sannier, X. Raepsaet, A. Terlain, V. Coen, A. Perujo, T. Sample, G. Benamati, P. Agostini

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2075-2080

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30027

Water-Cooled Lithium-Lead Blanket Design Studies for DEMO Reactor: Definition and Recent Developments of the Box-Shaped Concept

L. Giancarli, Y. Severi, L. Baraer, P. Leroy, J. Mercier, E. Proust, J. Quintric-Bossy

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2081-2088

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30028

Experimental Programme in Support of the Development of the European Ceramic-Breeder-Inside-Tube Test-Blanket: Present Status and Future Work

E. Proust, N. Roux, T. Flament, V. Levy, L. Anzidei, S. Casadio, G. Dell'Orco

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2089-2098

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30029

MHD Considerations for a Self-Cooled Liquid Lithium Blanket

D.K. Sze, R.F. Mattas, A.B. Hull, B. Picologlou, D.L. Smith

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2099-2106

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30030

Analysis of Bulk Shielding Experiments on Large SS316 Assemblies

F. Maekawa, C. Konno, K. Kosako, Y. Oyama, Y. Ikeda, H. Maekawa

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2107-2111

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30031

Activation Analysis for the D-³He Reactor ARIES-III

H. Y. Khater, M. E. Sawan

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2112-2116

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30032

Neutron Multiplication in Beryllium

J. Richard Smith

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2117-2122

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30033

Heat Transfer Correlations for Packed Beds

W. Fundamenski, P. Gierszewski

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2123-2127

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30034

Neutronics Aspects of ARIES-II and ARIES-IV Fusion Power Reactors

Laila A. El-Guebaly

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2128-2132

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30035

Neutronics Analysis for the Light Ion Beam Reactor LIBRA-LiTE

M. E. Sawan

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2133-2137

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30036

Envrionmental and Safety Aspects of “OSIRIS”: A Heavy Ion Beam Driven IFE Reactor

H. Y. Khater, M. E. Sawan, I. N. Sviatoslavsky, L. J. Wittenberg, W. R. Meier

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2138-2144

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30037

Pulsed/Intermittent Activation in Fusion Energy Reactor Systems

J. E. Sisolak, S. E. Spangler, D. L. Henderson

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2145-2151

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30038

Further Adaptation of the European Ceramic-B.I.T. Blanket Conceptual Design to Updated DEMO Specifications

B. Bielak, E. Proust, J. Szczepanski

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2152-2158

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30039

Activation Analysis for the Cavity of the PROMETHEUS ICF Design

Insoo Jim, Mohamed Abdou

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2159-2168

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30040

Bulk Shielding Experiments on Large SS316 Assemblies

C. Konno, F. Maekawa, Y. Ikeda, Y. Oyama, K. Kosako, H. Maekawa

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2169-2173

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30041

Analyses of 14 MeV Neutron Transport in Spherical Iron Assemblies with New Double-Differential ⁵⁶Fe Cross-Section Data

U. Fischer, E. Wiegner

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2174-2179

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30042

Measurements of Decay Radioactivity of Long-Lived Isotopes

A. Kumar, M.A. Abdou, M.Z. Youssef, Y. Ikeda, C. Konno, Y. Oyama, K. Kosako, F. Maekawa, H. Maekawa

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2180-2189

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30043

Measurement and Analysis of Nuclear Heat Depositions in Structural Materials Induced by D-T Neutrons

Y. Ikeda, C. Konno, K. Kosako, Y. Oyama, F. Maekawa, H. Maekawa, A. Kumar, M.Z. Youssef, M. A. Abdou

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2190-2196

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30044

Liquid Metal Flow Through a Right Angle Bend in a Strong Magnetic Field

L. Barleon, L. Bühler, K.J. Mack, R. Stieglitz, B.F. Picologlou, T.Q. Hua, C.B. Reed

Fusion Science and Technology / Volume 21 / Number 3P2B / May 1992 / Pages 2197-2203

Blanket Shield and Neutronic / dx.doi.org/10.13182/FST92-A30045