Progress on the conceptual design of a mirror hybrid fusion--fission reactor | Zendy

R.W. Moir | Zendy; J.D. Lee | Zendy; R.J. Burleigh | Zendy

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Progress on the conceptual design of a mirror hybrid fusion--fission reactor

Author(s) -

R.W. Moir,

J.D. Lee,

R.J. Burleigh

Publication year - 1975

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4182534

Subject(s) - fissile material , blanket , nuclear engineering , conceptual design , hybrid reactor , fission , fusion power , natural uranium , fusion , materials science , nuclear fission , rod , nuclear physics , uranium , neutron , plasma , physics , engineering , mechanical engineering , composite material , medicine , linguistics , philosophy , alternative medicine , pathology

A conceptual design study was made of a fusion-fission reactor for the purpose of producing fissile material and electricity. The fusion component is a D-T plasma confined by a pair of magnetic mirror coils in a Yin-Yang configuration and is sustained by neutral beam injection. The neutrons from the fusion plasma drive the fission assembly which is composed of natural uranium carbide fuel rods clad with stainless steel and helium cooled. It was shown conceptually how the reactor might be built using essentially present-day technology and how the uranium-bearing blanket modules can be routinely changed to allow separation of the bred fissile fuel. (MOW

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