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Division Spotlight
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.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
P. Greebler, B. A. Hutchins, R. B. Linford
Nuclear Technology | Volume 4 | Number 5 | May 1968 | Pages 297-306
Technical Paper and Note | doi.org/10.13182/NT68-A26395
Articles are hosted by Taylor and Francis Online.
The uncertainties in physics parameters and in fuel cost of fast power reactors due to current nuclear data uncertainties are considered for two sodium-cooled, oxide-fueled, 1000 MW(e) reactors. One reactor has a low core neutron leakage and a core composition that results in very low fuel cost and short doubling time for fissile material. The second reactor is forced to satisfy stringent safety criteria associated with the sodium voiding reactivity problem and, hence, has a high core neutron leakage and a large amount of moderating material (BeO) in its core composition, with resultant higher fuel cost. Ranges in uncertainties in fuel cost and doubling time for each recognized significant data uncertainty over a “correlated” energy interval are evaluated for each of the two reactors, using the highest and the lowest reasonable values of that nuclear data parameter, as well as the values recommended in the Brookhaven Evaluated Nuclear Data Files (ENDF/B). Combined uncertainties in data produce an uncertainty of ∼0.15 mill/kWh in fuel cost for the low leakage reactor and 0.25 mill/kWh for the reactor for which the design composition (BeO content) must be adjusted as the nuclear data are varied, in order to satisfy the stringent sodium voiding safety criteria. The current large uncertainty in the value of α for 239Pu below 15 keV is the largest single contributor to this overall fuel cost uncertainty, closely followed by the uncertainties in for 239Pu and σc(σc = σn,y) for 238U. On the basis of the calculated sensitivity of fuel cost to specific data uncertainties, a set of targets for nuclear data accuracy that would reduce the calculated fuel cost uncertainty to about ±0.03 mill/kWh is recommended.