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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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Fusion Science and Technology
When deployments hit setbacks: Cautionary tales in Idaho and Alaska
Plans announced with fanfare sometimes falter in the face of competition or economics. Take NuScale Power’s plans for the Carbon Free Power Project in Idaho: The project was canceled in mid-November by NuScale and its first customer, Utah Associated Municipal Power Systems, after nearly a decade. The significance of that news depends on the observer. NuScale intends to focus on other sites and customers. Competitors may redouble efforts to tout their own designs and customer lists. Media found an opportunity to speculate about the future of advanced nuclear. And while many in the nuclear community believe the momentum in favor of new nuclear deployments is continuing—or even increasing as COP28 continues—others would caution against high hopes and point to the persistent obstacles of regulation, supply chain constraints, and financing costs.
Troy Unruh, Benjamin Chase, Joy Rempe, David Nigg, George Imel, Jason Harris, Todd Sherman, Jean-François Villard
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 308-315
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT13-122
Articles are hosted by Taylor and Francis Online.
As part of an Idaho State University (ISU)–led Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) collaborative project that includes Idaho National Laboratory (INL) and the French Alternative Energies and Atomic Energy Commission (CEA), flux detector evaluations were completed to compare their accuracy, response time, and long-duration performance. Special fixturing, developed by INL, allows real-time flux detectors to be inserted into various Advanced Test Reactor Critical Facility (ATRC) core positions to perform lobe power measurements, axial flux profile measurements, and detector cross-calibrations. Detectors initially evaluated in this program included miniature fission chambers, specialized self-powered neutron detectors (SPNDs), and specially developed commercial SPNDs. Results from this program provide important insights related to flux detector accuracy and resolution for subsequent ATR and CEA experiments and yield new flux data required for benchmarking models in the ATR Life Extension Program (LEP) Modeling Update Project.