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Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Morris F. Osborne, Jack L. Collins, Richard A. Lorenz
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 157-169
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33994
Articles are hosted by Taylor and Francis Online.
Fission product release from fully irradiated light water reactor fuel under accident conditions and the chemical forms and behavior of the released material have been studied at high temperatures. This work has emphasized release from commercial fuels, but tracer-level tests using specific fission product species have been used in efforts to clarify chemical behavior. The specimens were heated in an induction furnace in flowing steam at temperatures of 1700 to 2300 K. The fractional releases of krypton, iodine, and cesium increased with temperature, reaching maxima of nearly 60% in 20 min. The release of tellurium varied strongly with the extent of cladding oxidation and approached that of cesium for completely oxidized cladding. In addition to some structural material, the major chemical forms in the furnace effluent appeared to include CsI, CsOH, silver, antimony, and tellurides of cesium and tin. The fractional releases of the volatile fission products correlated with the amount of fuel porosity, and the masses of aerosol collected increased with test temperature and oxidation. Comparison of our results with several fission product release models showed agreement ranging from good to poor.