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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.
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2020 ANS Virtual Winter Meeting
November 15–19, 2020
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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
NRC’s Inspector General issues report
Overall findings of a survey of Nuclear Regulatory Commission personnel indicate that while the NRC maintains a few strengths compared to external benchmarks, results have declined since 2015 in a number of areas, according to a recent report from the NRC’s Office of the Inspector General (OIG).
The survey was conducted in February 2020 by Willis Towers Watson, a global risk-management, insurance brokerage, and advisory firm that has partnered with the OIG for more than 20 years to assess the NRC’s safety culture and climate, as well as other aspects of employee experience.
S. Pelloni, J. Stepanek, D. J. Dudziaka)
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1189-1194
Neutronics and Shielding | dx.doi.org/10.13182/FST83-A23020
Articles are hosted by Taylor and Francis Online.
The European Community International Tokamak Reactor (INTOR-EC) was used to investigate the influence of different cross-section libraries on the tritium breeding ratio. Nucleonic analyses were performed using the discrete-ordinates transport codes ANISN and ONEDANT, and the recently developed Swiss surface-flux code SURCU. Nuclear data considered were from the DLC-37, VITAMIN-C (DLC-41 ), Los Alamos-NJOY and MACKLIB-IV fusion libraries. It is shown that very good agreement (within 0.5%) between the breeding ratios obtained using the VITAMIN-C and Los Alamos libraries could be obtained, whereas the corresponding values calculated using VITAMIN-C and MACKLIB-IV data sets collapsed into 25 neutron and 21 gamma groups differ up to 23%.
