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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
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.