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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Wayne R. Meier, Edward C. Morse
Fusion Science and Technology | Volume 8 | Number 3 | November 1985 | Pages 2665-2680
Technical Paper | Blanket Engineering | doi.org/10.13182/FST85-A24688
Articles are hosted by Taylor and Francis Online.
A method for optimizing the design of a fusion reactor blanket as a function of several design variables is described. Applications of the method are described elsewhere. The optimization problem consists of four key elements: a figure of merit (FOM) for the reactor, a technique for estimating the neutronic performance of the blanket as a function of the design variables, constraints on the design variables and neutronic performance, and a method for optimizing the FOM subject to the constraints. The FOM and constraints depend on the application and design objectives of the particular reactor concept. In general, they may be functions of the design variables and of the neutronic performance. A direct search, nonlinear simplex method is used to optimize the FOM subject to the constraints. The optimization algorithm requires the evaluation and comparison of the FOM at many different points in the search for the most attractive point. An evaluation of the neutronic performance is required each time a new point (i.e., a new set of design parameters) is chosen for comparison. The neutronic performance is evaluated by successive variational interpolation. With this approach, analytical expressions can be written for the neutronics performance as a function of the design variables based on only a limited number of reference point, neutron transport calculations. Hence, the FOM can be evaluated at any intermediate point without the need for additional transport calculations.