ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
Latest Magazine Issues
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
D. B. Lancaster, K. S. Smith, A. J. Machiels
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 57-70
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-28
Articles are hosted by Taylor and Francis Online.
The Electric Power Research Institute (EPRI) has sponsored the development of a set of benchmarks that can be used to quantify the bias and uncertainty in computed reactivity decrements due to burnup. The bias and uncertainty covers imprecision in both the nuclide inventory and cross sections. The EPRI benchmarks are a function of enrichment, operating conditions (such as soluble boron concentration, burnable absorbers, and specific power), and storage rack conditions. The benchmarks are analyzed using SCALE 6.1 with both ENDF/B-V and ENDF/B-VII cross-section libraries. The depletion analyses are performed using the TRITON module, and the criticality calculations are performed with KENO-V.a and MCNP. The analysis shows that SCALE 6.1 with the ENDF/B-VII 238-group cross-section library supports the use of a depletion bias of only 0.0015 in Δk, where k represents the neutron multiplication factor, at peak reactivity after discharge from the core. This peak reactivity occurs after 100 h of cooling. If credit is taken for more cooling, the bias should be increased to 0.0025. The depletion uncertainty is 0.0064. Using MCNP for the criticality calculations rather than KENO-V.a produces essentially the same results if the same ENDF/B cross-section library is used. Reliance on the ENDF/B-V cross-section library produces much larger disagreement with the benchmarks. The analysis covers numerous combinations of depletion and criticality options. In all cases, the historical uncertainty of 5% of the Δk of depletion (“Kopp memo”) was shown to be conservative for fuel with >30 GWd/T burnup. However, the Kopp memo's uncertainty may be exceeded at low burnups where the absolute magnitude of the uncertainty is small.