This report documents the second phase of critical experiment design (CED-2) conducted as part of integral experiment request (IER) 441. The purpose of IER-441 is to develop a capability to test the epithermal/intermediate cross sections of materials at the Sandia National Laboratories' (SNL's) critical experiment facility using low-enriched uranium oxide fuel. This effort determined that the capability can be achieved using a varying number of test samples in a central test region of a hexagonally pitched lattice driven with a more moderated exterior region. The hollow test region can be changed to either contain a pure aluminum wall or a wall that incorporates a cadmium thermal flux filter. This report documents the development of final anticipated critical configurations using tantalum as the test sample material. Using the anticipated critical configurations, estimates of the experimental uncertainties and sensitivities of materials are performed in keeping with the CEdT process. A list of the new hardware necessary to perform the experiment is included.

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This Critical Engineering Decision 1 report for the Integral Experiment Request 554 describes the effects of adding a commercially available neutron absorber material to a known light-water low-enriched uranium assembly. The assembly in question is the Seven Percent Critical Experiments at Sandia National Laboratories. The neutron absorber plates considered for the experiment are called Boralcan, which are made of boron carbide (B 4 C) particles embedded in 1100 aluminum alloy. The concentrations of B 4 C and 1100 aluminum, as well as the thickness and size of the plates, were changed, and the fuel rod configuration was adapted to ensure that the assembly would be critical in each case studied. A total of 10 critical configurations with a neutron absorber plate inserted are described in this report. No results of high-quality integral experiments involving neutron absorbers made with B 4 C and 1100 aluminum plates are currently publicly available. Sensitivity to the neutron absorber plate material definition, isotopes, and cross sections of specific regions and configurations are also analyzed. The study results indicate that these experiments are achievable with sufficiently low uncertainties and minimal modification to the assembly. The experimental uncertainty can be further decreased with an additional characterization of the plates by x-ray computerized tomography or neutron radiography methods.

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