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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Stanislav P. Simakov, Boris V. Devkin, Michael G. Kobozev, Ulrich von Möllendorff, Dimitriy Yu. Chuvilin
Fusion Science and Technology | Volume 36 | Number 2 | September 1999 | Pages 173-180
Technical Paper | doi.org/10.13182/FST99-A100
Articles are hosted by Taylor and Francis Online.
The results of a transmission experiment on a spherical nickel shell with a 7.5-cm-thick wall and a 14-MeV neutron point source at the center are reported. The neutron leakage spectrum from 14 MeV down to 100 keV was measured by the time-of-flight (TOF) method. Descriptions of the experimental arrangement, TOF spectrometer, measurements, and data-reduction procedures are given. The measured data are compared with results obtained in other laboratories. Three-dimensional Monte Carlo calculations with the MCNP code using the FENDL-1, EFF-2.4, and JENDL-FF nuclear data libraries were made. The FENDL-1 library predicted the neutron leakage from nickel more accurately than the other libraries.
