ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
The newest era of workforce development at ANS
As most attendees of this year’s ANS Annual Conference left breakfast in the Grand Ballroom of the Chicago Downtown Marriott to sit in on presentations covering everything from career pathways in fusion to recently digitized archival nuclear films, 40 of them made their way to the hotel’s fifth floor to take part in the second offering of Nuclear 101, a newly designed certification course that seeks to give professionals who are in or adjacent to the industry an in-depth understanding of the essentials of nuclear energy and engineering from some of the field’s leading experts.
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.