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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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Latest News
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
Robert E. Price, Geoffrey W. Shuy, James T. Woo
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1412-1417
Machine Upgrades and Next-Generation Devices | doi.org/10.13182/FST86-A24926
Articles are hosted by Taylor and Francis Online.
In the present scenario for the development of magnetic confinement fusion, the availability of tritium needed to fuel a D-T burning plasma in order to generate 14 MeV neutrons for material and system component testing is not being fully addressed. An alternate approach based on the in situ generation of tritium in a driven D-D reacting plasma is proposed. The feasibility of this approach to attain 14 MeV neutron flux levels comparable with D-T fueled burning plasma from a modest beta, first generation fusion power reactor can be established from known results. A staged scenario, is described in which tritium bred from developmental blankets is used to fuel the system to incrementally raise the neutron wall loading to simulate more advanced fusion reactors.