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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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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
Gerald Kamelander
Nuclear Science and Engineering | Volume 83 | Number 4 | April 1983 | Pages 507-513
Technical Note | doi.org/10.13182/NSE83-A18656
Articles are hosted by Taylor and Francis Online.
The Monte Carlo theory provides a powerful tool for solving three-dimensional neutron shielding problems. Special variance reducing methods must be applied if the detector regions are very remote from the source region. Recently, an idea for a new scoring method was proposed to reduce an estimator for large distances between flux point and collision point to the standard flux point estimator. A Monte Carlo code based on this method was developed. This code was applied to the calculation of neutron doses, neutron spectra, and neutron fluxes produced by the detonation of an enhanced radiation weapon. The results may be considered as a test of the efficiency and as a first application of a new Monte Carlo method. The radiation doses reported in this Note only refer to neutrons. The gamma-ray radiation doses due to neutron capture reactions are not considered.