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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Framatome begins expansion of facilities in Virginia
An official groundbreaking last week at Framatome’s Mill Ridge Road facility, in Lynchburg, Va., marks the start of a $50 million expansion and an eventual addition of 500 employees, according to the nuclear company.
Mark L. Williams
Nuclear Science and Engineering | Volume 155 | Number 1 | January 2007 | Pages 18-36
Technical Paper | doi.org/10.13182/NSE06-11
Articles are hosted by Taylor and Francis Online.
Equations for sensitivity coefficients of eigenvalue-difference responses such as reactivity are derived from a unified approach based on both eigenvalue and generalized perturbation theory. The sensitivity coefficients are utilized for uncertainty analysis of reactivity responses, and it is shown that these types of responses have inherently larger relative uncertainties than eigenvalue responses. Monte Carlo calculations are used to apply the methodology to the analysis of the coolant void reactivity in a three-dimensional model of a fuel bundle in an advanced CANDU reactor system. The important data sensitivities are identified, and it is shown that the coolant void reactivity has a large uncertainty due to nuclear data uncertainties.