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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
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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.
Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 71-91
Technical Note | Fission Reactors | doi.org/10.13182/NT14-109
Articles are hosted by Taylor and Francis Online.
Characterization of graphite particles (dust) produced by the rotational abrasion that would occur in a shifting pebble bed reactor is of interest for purposes of maintenance, safety, and operation. To better understand this type of particle generation, we have modified and used our existing test apparatus to achieve rotational abrasion in a 1% to 5% relative humidity air environment. We have used both a commercial, nonnuclear-grade graphite (GM-101 from Graphtek, LLC) and a nuclear-grade graphite (MLRF1 from SGL Carbon, Ltd.). In both cases, we used two spheres with one being held stationary and with the other being rotated while under load and in contact with the first. We have obtained size distributions for the abraded particles. We have also fit lognormal functions to those size distributions (for use in nuclear computer codes); determined particle shapes; measured chamber temperature and humidity during the tests; measured and calculated wear rates of the spheres; measured the surface roughness of both pretest and posttest samples; and measured particle surface areas, pore volumes, and pore volume distributions of the particles produced during the abrasion of the graphite surfaces under different loadings and with different rotating speeds. We also carried out additional tests to measure the surface temperature near the contact point. The experiments showed that as loading (analogous to pebble depth in the reactor) and rotation speeds increase, so do wear rates, concentrations of particles, and particle surface area. The shape of the dust particles was in every case nonspherical, as one would expect. The surface area of bulk GM-101 graphite is ∼0.58 m2·g−1, and the surface area of bulk MLRF1 is ∼2.78 m2·g−1. After testing, abraded particle surface areas were observed to increase to 493 m2·g−1 for GM-101 and to 545 m2·g−1 for MLRF1. Wear rates of the spheres during testing were observed to range from 0.003 to 0.07 g min−1 per contact site. The upper limit on the size of the abraded particles that was observed was less than ∼4000 nm.