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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Fusion Science and Technology
Latest News
BWXT announces nuclear manufacturing plant expansion
BWX Technologies announced today plans to expand and add advanced manufacturing equipment to its manufacturing plant in Cambridge, Ontario, Canada.
A $36.3 million USD ($50M CAD) expansion will increase the plant’s size by 25 percent—to 280,000 square feet—and another $21.7 million USD ($30M CAD) will be spent on new equipment to increase and accelerate its output of large nuclear components. The investment will increase capacity and create more than 200 long-term jobs for skilled workers, engineers, and support staff, according to the company.
M. Angelone, P. Batistoni, F. Moro, M. Pillon, R. Villari, M. Loughlin
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 124-128
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13377
Articles are hosted by Taylor and Francis Online.
A mock-up of the inboard shield and vacuum vessel of ITER was set up at ENEA Frascati and irradiated with 14-MeV neutrons produced by the Frascati Neutron Generator. The mock-up includes the coil region, and its dimensions and materials composition are consistent with the latest ITER design. The objective of the experiment is to validate the calculations of nuclear heating in the ITER toroidal field coil performed with the Monte Carlo code MCNP-5 and the FENDL-2.1 library, through measurement performed by thermoluminescent dosimeters. The goal was to reach a calculated-to-experiment accuracy of less than or equal to ±10%, possibly as low as ±8%.