ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
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.
Maurizio Angelone, Paola Batistoni, Marcello Martone, Mario Pillon, Massimo Rapisarda, Sofia Rollet
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 431-439
Technical Paper | Experimental Device | doi.org/10.13182/FST91-A29383
Articles are hosted by Taylor and Francis Online.
The Frascati Tokamak Upgrade (FTU) neutron activation system has been calibrated using indium foils and a 252Cf spontaneous fission neutron source located at several positions within the tokamak. The same experimental arrangements have been simulated with the MCNP Monte Carlo neutron and photon transport code in order to numerically reproduce the activation response coefficients measured experimentally. The main purpose of the comparison is to assess the accuracy of the numerical simulation and of the modeling of the FTU device. This analysis has a more general relevance in view of the use of the activation system as an independent method for the absolute measurement of the neutron yield in next-step fusion devices. An overall agreement at the 22% level between experiment and calculation has been demonstrated.
