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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Experimenters get access to NSUF facilities for irradiation effects studies
The Department of Energy’s Office of Nuclear Energy announced the recipients of “first call” 2025 Nuclear Science User Facilities (NSUF) Rapid Turnaround Experiment (RTE) awards on June 26. The 23 proposals selected from industry, national laboratories, and universities will receive a total of about $1.4 million. While each project is led by a different principal investigator, some call the same organization home. A total of 17 companies, labs, and universities are represented.
Selena Ng, Dominique Grenèche, Bernard Guesdon, Richard Vinoche, Marc Delpech, Florence Dolci, Hervé Golfier, Christine Poinot-Salanon
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 13-19
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4004
Articles are hosted by Taylor and Francis Online.
Introducing neptunium into the nuclear fuel cycle has been proposed in the past as a way to impede the diversion or the direct use of plutonium to fabricate a nuclear explosive device. This paper aims to technically analyze the industrial consequences should this proposal be implemented. Two scenarios are considered: (a) adding neptunium to fresh uranium oxide (UOX) fuel before irradiation in a light water reactor (LWR) and (b) separating neptunium together with plutonium from used UOX fuel and using this combined oxide to fabricate mixed oxide (MOX) fuel before subsequent irradiation in an LWR. In both cases, assembly calculations for a pressurized water reactor using fresh fuel doped with neptunium are presented for a wide range of neptunium proportions. The consequences on the core and fuel performance and the fuel cycle are analyzed. The analysis shows that while irradiating neptunium-doped UOX fuel can offer significant proliferation-resistance benefits because of the increased quantity of the plutonium isotope 238Pu in the discharged fuel, it entails heavy industrial penalties even at 1% Np content. The use of neptunium with MOX fuel is limited to 0.5% in order to maintain a negative void coefficient. At this proportion, it offers minimal increase in 238Pu content, and it is unlikely that detectability through gamma-ray emissions of the resulting plutonium-neptunium oxide mixture is increased. The fact that neptunium itself may pose a proliferation risk must be carefully weighed in any decision to use neptunium as a tool to increase proliferation resistance.