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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
R. Stephen Devoto, William L. Barr, Richard H. Bulmer, Robert B. Campbell, Max E. Fenstermacher, Joseph D. Lee, B. Grant Logan, John R. Miller, Louis L. Reginato, R. A. Krakowski, Ronald L. Miller, Oscar A. Anderson, W. S. Cooper, Joel H. Schultz, James J. Yugo, Joel H. Fink, Yousry Gohar
Fusion Science and Technology | Volume 19 | Number 2 | March 1991 | Pages 251-272
Technical Paper | Fusion Reactor | doi.org/10.13182/FST91-A29363
Articles are hosted by Taylor and Francis Online.
The extensions of the physics and engineering guidelines for the International Thermonuclear Experimental Reactor (ITER) device needed for acceptable operating points for a steady-state tokamak power reactor are examined. Noninductive current drive is provided in steady state by high-energy neutral beam injection in the plasma core, lower hybrid slow waves in the outer regions of the plasma, and bootstrap current. Three different levels of extension of the ITER physics/engineering guidelines, with differing assumptions on the possible plasma beta, elongation, and aspect ratio, are considered for power reactor applications. Plasma gain Q = fusion power/input power in excess of 20 and average neutron wall fluxes from 2.3 to 3.6 MW/m2 are predicted in devices with major radii varying from 7.0 to 6.0 m and aspect ratios from 2.9 to 4.3. Only modest enhancements over L-mode (Goldston) energy confinement are required. Peak divertor heat fluxes range up to 12.4 MW/m2, which is somewhat higher than the current ITER design limit of 10 MW/m2 with a magnetically swept divertor. These designs were selected on the basis of improvements in physics/engineering consistent with time scales for development of future reactors. The design reoptimization on the basis of cost of electricity (COE) was then examined using a reactor systems model. This analysis generally verified the original estimates for the required extensions of the ITER guidelines. The COE is projected to be <66 mill/kW(electric) · h in all of the configurations. The smallest reactor, which has the largest neutron wall flux and mass power density, yields the lowest COE, 56 mill/kW(electric)· h. While these costs are marginally competitive with fission power, these modest extensions of the ITER guidelines do produce a viable power reactor. With time for further improvements such as those pursued in the ARIES study, similar designs could present an even more competitive commercial product.