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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
ANS, UCOR sign MOU for workforce development program
The American Nuclear Society and United Cleanup Oak Ridge have signed a memorandum of understanding that establishes a framework for collaboration to advance ANS workforce training and certification programs serving the nuclear industry.
According to the document, UCOR will provide “operational insights and subject matter expertise to inform ANS’s professional development and credentialing offerings, including the Certified Nuclear Professional [CNP] program.” The collaboration will strengthen UCOR’s workforce development efforts while advancing ANS’s mission to sustain and expand the national nuclear workforce pipeline and capabilities.
R. C. Lloyd, E. D. Clayton, L. E. Hansen, S. R. Bierman
Nuclear Technology | Volume 18 | Number 3 | June 1973 | Pages 225-230
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31297
Articles are hosted by Taylor and Francis Online.
A series of criticality experiments was performed on plutonium nitrate solutions in slab geometry. The solutions contained plutonium at concentrations ranging between 58 and 412 g Pu/liter for material with three different isotopic contents: 4.6, 18.4, and 23.2 wt% 240Pu. Acid molarities varied from 1.6 to 5.0. The experiments were performed with a variable thickness slab-type vessel of 42-in. height and width, whose thickness could be adjusted throughout a range of 3 to 9 in. The experimental vessel was used with and without a water reflector and also with a 1-in.-thick Plexiglas reflector. The critical experiment data from the finite slabs were corrected to yield values of critical thicknesses for one-dimensional infinite slabs, i.e., slabs of finite thickness but of infinite height and width. Analytical corrections, based on experimental data, were subsequently used to correct the critical infinite slab thicknesses for materials extraneous to the plutonium solutions, such as the effect of the stainless-steel vessel walls and room return neutrons. The analysis provided values for clean one-dimensional assemblies that were then used as an integral check of calculational methods using cross sections from the ENDF/B-II data file. The computed values of keff for these “clean assemblies” ranged between 0.988 and 1.040; the values increased somewhat with increasing concentration.