Oak Ridge EPR reference design

Conference · Wed Jan 01 04:00:00 EST 1975

OSTI ID:4153530

Roberts, M

A Tokamak EPR reference design is presented as a basis for further study leading to a conceptual design. The set of basic plasma parameters selected, namely, minor radius of 2.25 m, major radius of 6.75 m, magnetic field on axis of 4.8 T and plasma current of 7.2 MA, should produce a reactor-grade plasma with a significant neutron flux even with the large uncertainty in plasma physics scaling from present experience to large sizes. Neutronics and heat transfer calculations coupled with mechanical design and materials considerations were used to develop a blanket and shield capable of operating at high temperature, protecting the surrounding coils, being maintained remotely and, in a few experimental modules, breeding tritium. The toroidal field coil design developed for a maximum field of 11 T at the winding combines the use of multifilamentary Nb$sub 3$Sn and NbTi superconducting cables (in high and low field regions, respectively) with forced flow of supercritical helium enclosed in a steel conduit. The poloidal magnetics system is specially designed both to reduce the total volt-second energy requirements and to reduce the rate of field change at the toroidal field coils. The reference design was synthesized from the information developed and evaluated in our prior scoping study. (auth)

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• NSA Number: NSA-33-007102
• OSTI ID: 4153530
• Report Number(s): CONF-751125--60
• Country of Publication: United States
• Language: English

Related Subjects

*TOKAMAK DEVICES-- DESIGN
700200* --Fusion Energy--Fusion Power Plant Technology
BREEDING BLANKETS
HEAT TRANSFER
N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
NEUTRON REACTIONS
SHIELDING
SUPERCONDUCTING MAGNETS