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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 617-627
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT85-A33684
Articles are hosted by Taylor and Francis Online.
Measurements of thermal and nonthermal neutron streaming were taken throughout the medical irradiation room and the two-legged labyrinth of the Musashi Institute of Technology Research Reactor (the Musashi reactor) by using a rem counter. The length of the measured line was 8 m. The measurements were also analyzed by using the Monte Carlo coupling technique. The contribution of nonthermal neutrons was obtained with a cadmium-covered rem counter and that of thermal neutrons was obtained from the difference between the responses measured with and without the cadmium cover. The response ratio of total neutrons to nonthermal neutrons is constant for the straight part of the duct and increases rapidly around the bent portion. The constant values of the response ratio are 2, 3, and 5 for the first, second, and third legs, respectively. The value of 1.5 count / s = 1 mrem / h was used as the coefficient for conversion to the neutron dose rate. The discrepancies between the measured and calculated results are within ∼50% for the nonthermal neutron response, and within a factor of 2 for total neutron response. The fractional standard deviations of the Monte Carlo calculations are 0.07 to 0.12 and 0.13 to 0.24 in the first leg, 0.07 to 0.18 and 0.13 to 0.44 in the second leg, and 0.12 to 0.38 and 0.17 to 0.56 in the third leg for nonthermal and total neutron dose rates, respectively.