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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
Work advances on X-energy’s TRISO fuel fabrication facility
Small modular reactor developer X-energy, together with its fuel-developing subsidiary TRISO-X, has selected Clark Construction Group to finish the building construction phase of its advanced nuclear fuel fabrication facility, known as TX-1, in Oak Ridge, Tenn. It will be the first of two Oak Ridge facilities built to manufacture the company’s TRISO fuel for use in its Xe-100 SMR. The initial deployment of the Xe-100 will be at Dow Chemical Company’s UCC Seadrift Operations manufacturing site on Texas’s Gulf Coast.
S. S. Glickstein, P. H. Lehmann, L. L. Wheat, J. D. Korsmeyer, S. Milani, G. G. Smith, S. H. Weiss
Nuclear Science and Engineering | Volume 30 | Number 1 | October 1967 | Pages 122-136
Technical Paper | doi.org/10.13182/NSE67-A17249
Articles are hosted by Taylor and Francis Online.
Thermal disadvantage factor measurements in cells of seed-blanket assemblies containing highly enriched 235U and 233U fuel rods as well as in cells containing slightly enriched 233U fuel rods are in agreement within experimental uncertainties with calculations for all but a very tightly packed blanket lattice. The measurements were corrected for flux perturbations in the fuel rod and the moderator channel caused by the detecting foils. MARC calculations using the Radkowsky scattering kernel yield results approximately 8% higher than similar calculations using the Nelkin kernel. While THERMOS calculations for the tightly packed blanket cells appear to be in agreement with measurement (possibly fortuitous), MARC results are significantly above the measured values. The source of the discrepancy is not known at this time. Higher order scattering as well as angular energy effects in the source-to-thermal neutron energy treatment have been investigated using a newly developed full energy range (0 to 10 MeV) Monte Carlo program RECAP-4C.
