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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Joshua Peterson, Erich Schneider
Nuclear Science and Engineering | Volume 173 | Number 1 | January 2013 | Pages 28-42
Technical Paper | doi.org/10.13182/NSE11-49
Articles are hosted by Taylor and Francis Online.
A modified form of first-order perturbation theory, called phase-space interpolated perturbation theory (PSIPT), was developed to more accurately model families of perturbations where changes are intermediate to defined reference and bounding configurations. PSIPT can thus be used on any application where the range of change to the system is known a priori but the magnitude of change is not known. PSIPT is demonstrated for several applications, notably the position of the outer shim control cylinders (OSCCs) at the Advanced Test Reactor (ATR). The current method used for calculating the OSCC positions during a cycle startup utilizes a heuristic trial-and-error approach that is impractical with advanced computationally intensive reactor physics tools. PSIPT is implemented into a method to automate shim rotation prediction for startup.