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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
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Christopher R. Hughes, Oswaldo Pelaez, Duwayne Schubring, Kelly A. Jordan
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 292-300
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-74
Articles are hosted by Taylor and Francis Online.
This work concerns the comparison of supercritical water reactor (SCWR) assembly designs using coupled reactor physics and thermal-hydraulic methods. In the SCWR, large density gradients in the supercritical water (used as coolant and moderator) will require detailed multiphysics analysis. The Super Light Water Reactor (SLWR) was analyzed previously [Hughes et al., Nucl. Eng. Des., Vol. 270 (2014)], where MCNP5 was coupled with density and temperature results from a single-channel code. MCNP5 then provided the single-channel code with a linear heat profile. In the present work, that proposed assembly design is determined to have a negative density coefficient of reactivity. Two alternate designs with different geometries and water-to-fuel ratios are presently considered to address this issue. It is found that adding an additional row of pins is more effective at producing a positive density coefficient than is reducing the size of the moderator boxes.