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Division Spotlight
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.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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Nuclear Science and Engineering
June 2023
Nuclear Technology
Fusion Science and Technology
July 2023
Latest News
NRC advisors give nod to Hermes construction permit
Having completed its review of the construction permit application for Kairos Power’s Hermes test reactor early last month, the Nuclear Regulatory Commission’s Advisory Committee on Reactor Safeguards (ACRS) recently submitted its conclusions to the agency, recommending approval.
Weston M. Stacey
Nuclear Technology | Volume 200 | Number 1 | October 2017 | Pages 15-26
Technical Paper | doi.org/10.1080/00295450.2017.1345585
Articles are hosted by Taylor and Francis Online.
The Georgia Tech concept of the Subcritical Advanced Burner Reactor (SABR) spent nuclear fuel (SNF) transmutation reactor and supporting analyses to date are summarized. SABR is based on the fast reactor physics and technology prototyped in Experimental Breeder Reactor-II (EBR-II) and proposed for the Integral Fast Reactor and the PRISM Reactor and on the tokamak fusion neutron source physics and technology that will be prototyped in ITER. Preliminary fuel cycle calculations indicate that subcritical operation would enable a proliferation-resistant fuel reprocessing cycle that would safely accommodate fuel with up to 100% TRU content and that introduction of SABRs in a 1-to-3 power ratio with light water reactors would reduce the required SNF high-level waste repository capacity (defined on the basis of decay heat released) by a factor of 10 to 100. Preliminary dynamic safety calculations indicate that SABRs could be shut down to the decay heat level by turning off the plasma heating power without core damage in loss of heat sink, loss of flow, and loss of power accidents, but that additional decay heat removal capability is needed in the case of total loss of primary or secondary system pumping power.