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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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, M. A. Abdou, M. Z. Youssef, C. Konno, K. Kosako, Y. Oyama, T. Nakamura, H. Maekawa
Fusion Science and Technology | Volume 28 | Number 1 | August 1995 | Pages 173-215
Technical Paper | Fusion Neutronics Integral Experiments — Part I / Blanket Engineering | doi.org/10.13182/FST95-A30405
Articles are hosted by Taylor and Francis Online.
Experimental measurement of nuclear heating rates was carried out in a simulated D-T fusion neutron environment from 1989 through 1992 under the U.S. DOE/JAERI collaborative program at the Fusion Neutronics Source Facility. Small probes of materials were irradiated in close vicinity of a rotating target. A sophisticated microcalorimetric technique was developed for on-line measurements of total nuclear heating in a mixed neutron plus photon field. Measurements with probes of graphite, titanium, copper, zirconium, niobium, molybdenum, tin, tungsten, and lead are presented. These measurements have been analyzed using the three-dimensional Monte Carlo code MCNP and various heating number/kerma factor libraries. The ratio of calculated to experimental (C/E) heating rates shows a large deviation from 1 for all the materials except tungsten. For example, C/E's for graphite range from 1.14 (σ = 10%) to 1.36 (10%) for various kerma factor libraries. Uncertainty estimates on total nuclear heating using a sensitivity approach are presented. Interestingly, C/E data for all libraries and materials can be consolidated to obtain a probability density distribution of C/E's that very much resembles a Gaussian distribution centered at 1.04. The concept of “quality factor” is defined and elaborated so as to take cognizance of observed uncertainties on prediction of nuclear heating for all the nine materials.