Fusion Engineering and Design

Preface
pp. ix-ix(1)

Overview of the Japanese fusion reactor studies programme
pp. 247-254(8)
Author: Seki Y.

Spherical tokamak power plant design issues
pp. 255-263(9)
Authors: Hender T.C.; Bond A.; Edwards J.; Karditsas P.J.; McClements K.G.; Mustoe J.; Sherwood D.V.; Voss G.M.; Wilson H.R.

The advanced SSTR
pp. 265-270(6)
Authors: Kikuchi M.; Seki Y.; Nakagawa K.

Prototype tokamak fusion reactor based on SiC/SiC composite material focusing on easy maintenance
pp. 271-279(9)
Authors: Nishio S.; Ueda S.; Kurihara R.; Kuroda T.; Miura H.; Sako K.; Takase H.; Seki Y.; Adachi J.; Yamazaki S.; Hashimoto T.; Mori S.; Shinya K.; Murakami Y.; Senda I.; Okano K.; Asaoka Y.; Yoshida T.

Physics basis for a tokamak fusion power plant
pp. 281-298(18)
Authors: Jardin S.C.; Bathke C.G.; Ehst D.A.; Kaye S.M.; Kessel C.E.; Lee B.J.; Mau T.K.; Menard J.; Miller R.; Najmabadi F.

Study of a spherical torus based volumetric neutron source for nuclear technology testing and development
pp. 299-306(8)
Authors: Cheng E.T.; Cerbone R.J.; Sviatoslavsky I.N.; Galambos L.D.; Peng Y.-K.M.

Assessment of the gas dynamic trap mirror facility as intense neutron source for fusion material test irradiations
pp. 307-325(19)
Authors: Fischer U.; Moslang A.; Ivanov A.A.

On design and development issues for the FRC and related alternate confinement concepts
pp. 327-337(11)
Authors: Miley G.H.; F. Santarius J.; Steinhauer L.

A new poloidal-bundle divertor for a spherical tokamak
pp. 339-345(7)
Authors: Ogawa Y.; Yamamoto T.; Yonezawa K.; Ohyabu N.

The feasibility of a tokamak reactor with a very high aspect ratio plasma
pp. 347-354(8)
Authors: Murakami Y.; Shinya K.; Nishio S.

Neutronics on inertial fusion reactors
pp. 355-370(16)
Authors: Perlado J.M.; Sanz J.

Blanket system selection for the ARIES-ST
pp. 371-378(8)
Authors: Sze D.-K.; Tillack M.; El-Guebaly L.

Blanket and first wall conceptual design issues of the spherical tokamak power plant
pp. 379-387(9)
Authors: Karditsas P.J.; Edwards J.E.G.

A helium-cooled blanket design of the low aspect ratio reactor
pp. 389-396(8)
Authors: Wong C.P.C.; Baxi C.B.; Cerbone R.; Cheng E.T.; Reis E.E.

Conceptual design of a breeding blanket with super-heated steam cycle for CREST-1
pp. 397-405(9)
Authors: Asaoka Y.; Okano K.; Yoshida T.; Tomabechi K.; Ogawa Y.; Sekimura N.; Fukai Y.; Hatayama A.; Inoue N.; Kohyama A.; Yamazaki S.-i.; Mori S.

Toroidal field coil design for the spherical tokamak power plant
pp. 407-418(12)
Authors: Voss G.M.; Bond A.; Edwards J.E.G.; Hender T.C.

SEAFP-2 bounding accident analyses
pp. 419-433(15)
Authors: Taylor N.P.; Cook I.; Forty C.B.A.; Han W.E.; Taylor P.

Composition adjustment of low activation materials for shallow land burial
pp. 435-441(7)
Authors: Seki Y.; Tabara T.; Aoki I.; Ueda S.; Nishio S.; Kurihara R.

EC long-term studies on fusion waste management
pp. 443-453(11)
Authors: Rocco P.; Broden K.; Forrest R.A.; Forty C.B.A.; Lindberg M.; Zucchetti M.

Waste management aspect of low activation materials
pp. 455-465(11)
Author: Cheng E.T.

Assessing a new direction for fusion
pp. 467-472(6)
Author: Waganer L.M.

Birth to death analysis of the energy payback ratio and CO₂ gas emission rates from coal, fission, wind, and DT-fusion electrical power plants
pp. 473-481(9)
Authors: White S.W.; Kulcinski G.L.

Energy analysis and carbon dioxide emission of Tokamak fusion power reactors
pp. 483-498(16)
Authors: Tokimatsu K.; Hondo H.; Ogawa Y.; Okano K.; Yamaji K.; Katsurai M.

European structural materials development for fusion applications
pp. 499-508(10)
Authors: van der Schaaf B.; Ehrlich K.; Fenici P.; Tavassoli A.A.; Victoria M.

R&D issues for SiC_f/SiC composites structural material in fusion power reactor blankets
pp. 509-520(12)
Authors: Giancarli L.; Aiello G.; Caso A.; Gasse A.; Le Marois G.; Poitevin Y.; Salavy J.F.; Szczepanski J.

Maintenance and material aspects of DREAM reactor
pp. 521-526(6)
Authors: Ueda S.; Nishio S.; Yamada R.; Seki Y.; Kurihara R.; Adachi J.; Yamazaki S.; Design Team D.

Analysis of irradiation creep and the structural integrity of fusion in-vessel components
pp. 527-537(11)
Author: Karditsas P.J.