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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.
Meeting Spotlight
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
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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Latest News
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.
A. Kumar, Y. Ikeda, C. Konno
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1979-1988
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29632
Articles are hosted by Taylor and Francis Online.
The experimental measurement of nuclear heat deposition rates in a simulated D-T fusion neutron environment has assumed importance due to untested nature of large body of kerma factor libraries. An experimental effort was recently initiated to develop and apply calorimetric technique to measure heat deposition in various materials subjected to D-T neutron fields, in the framework of JAERI/USDOE collaborative program on fusion neutronics. Thermistors and platinum RTD's were employed as thermal sensors within calorimeters made of single materials (or probes). The first experiments were conducted during June 1989 and the tested materials included: Fe, Al, C, Cu. Each of these calorimeters was placed inside a vacuum chamber and the mean distance from the target was ∼8 cm. The calorimeters were subjected to spaced neutron pulses of 3 to 10 min duration. The measured heat deposition rates ranged from 7 to 30 µW/g for a normalized source strength of 1012 n/s-iron and graphite providing the lowest and the highest rates respectively. These single probe experiments were analyzed using 3D code MCNP. The single probe experiments were carried out again in december 1989. This allowed to verify the reproducibility. This time, the average target-probe distance was shortened to ∼5 cm which led to 2 to 3 times higher rates. Tungsten was also included. Ratio of computed (C) to measured (E) rates varied from 0.79 to 1.77 for RMCCS evaluation of MCNP. Four evaluations, available with MCNP, throw up large deviations; For example, C/E for iron for an experiment ranges from 0.40 to 0.94. In addition to single probe experiments, two novel experiments were conducted with multiple probes in separate host media of iron and graphite. C/E varied from 0.51 to 2.36.