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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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Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
Justin Mart, Andrew Klein, Alexey Soldatov
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 8-19
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-135
Articles are hosted by Taylor and Francis Online.
The elimination of soluble boron in the operation of small modular integral pressurized water reactors creates several advantages. Most of these advantages are realized by the core simplification brought on by removing the corrosive effects of soluble boron. Piping, pumps, and tanks associated with soluble boron can be completely eliminated, bringing a significant economic and safety benefit. Additionally, a whole class of accidents related to boron dilution would be eliminated by design, and any loss-of-coolant event would not be affected by the presence of soluble boron. However, removing soluble boron creates its own set of specific challenges that must be overcome. In traditional pressurized water reactors, soluble boron is used in conjunction with burnable poisons to suppress excess initial reactivity. Since boron is diluted in the coolant, its presence is felt uniformly throughout the core, and thus it uniformly reduces the excess initial reactivity. In any boron-free design, an acceptable alternative to boron must be found through the use of the other two mechanisms for reactivity control: burnable poisons and control rods. However, both methods pose challenges. Control rods are actively controlled but are discrete absorbers, locally impacting the core where they are inserted. Since they are inserted from the top of the core, their presence negatively impacts the axial neutron flux profile. This axial flux imbalance creates undesirable peaking factors, leading to reduced operating margins. Thus, the main challenge in any boron-free design concerns excess reactivity suppression and active reactivity control while maintaining a proper axial flux profile and reduced peaking factors. This paper demonstrates that an advanced control rod algorithm with multiple control rod banks can be used for this purpose to satisfy the criteria for success.