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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
John N. Hamawi
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 363-370
Technical Note | doi.org/10.13182/NT16-18
Articles are hosted by Taylor and Francis Online.
Estimates of radiation doses to receptors in the vicinity of nuclear power plants from gaseous effluents are important to ensure that plant operation is in compliance with the as-low-as-reasonably-achievable dose objectives delineated in 10 CFR 50, Appendix I. The U.S. Nuclear Regulatory Commission (NRC) recently issued an Advance Notice of Proposed Rulemaking (ANPR) on the development of a new regulatory basis in support of aligning the NRC regulations governing dose assessments for radioactive effluents with the most recent methodology published by the International Commission on Radiological Protection (ICRP) contained in ICRP Publication 103 (ICRP-103) (2007). The ANPR specifically recommends that the dose conversion factors (DCFs) in Regulatory Guide 1.109 (RG 1.109) be revised as part of any effort to more closely align the NRC’s regulations with the ICRP-103 recommendations. Section C.2 of RG 1.109 provides a sector-average (SA) finite-cloud model for computation of annual doses at off-site receptors from noble gas releases from freestanding tall stacks. One of the limitations of this model is that embedded in the applicable equation is the DCF, and as such, the model is not suitable for implementation of the ANPR (if approved) and the recommended use of stand-alone updated DCFs. This limitation can be circumvented through use of the “gamma atmospheric dispersion factor” in the finite-cloud dose model, referred to as the gamma (χ/Q). A second limitation of the SA finite-cloud model is the dose overestimation at close-in receptors under very stable conditions and elevated plumes, which can be eliminated by using the corresponding finite-cloud gamma (χ/Q) for the plume-centerline (PC) model. Presented are analytical details on the derivation and use of the SA and PC gamma (χ/Q)’s, which are suitable for incorporation of stand-alone updated sets of DCFs based on ICRP-103.