Analysis of the 30B UF&lt;sub&gt;6&lt;/sub&gt; Container for Use with Increased Enrichment

Saylor, Ellen Marie; Lang, Alex; Marshall, William B.J.; Hall, B. R.

doi:10.2172/1797631

Cited by 1 publication

(1 citation statement)

References 7 publications

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“…To determine comprehensive lists of potential accident scenarios for the transportation of the VP-55 package, IAEA safety standard TS-R-1 "Regulations for the Safe Transport of Radioactive Materials" [6], 10 CFR Part 71 "Packaging and Transportation of Radioactive Materials" [11], and several criticality safety studies [4,14,15] were reviewed. The scenarios are similar those identified for the DN30-X cylinder, with additional consideration of the graphite material in the fuel pebbles.…”

Section: Fuel Pebble Transportationmentioning

confidence: 99%

Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration

Bostelmann,

Davidson,

Wieselquist

et al. 2023

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To assess the modeling and simulation capabilities for radionuclide characterization, criticality, and shielding in the nuclear fuel cycle of non-light-water reactor (LWR) technologies, the US Nuclear Regulatory Commission (NRC) initiated a collaborative project between the NRC, Sandia National Laboratories (SNL), and Oak Ridge National Laboratory (ORNL) with the goal to demonstrate capabilities of MELCOR and SCALE to calculate accident scenarios in all stages of the nuclear fuel cycle for relevant non-LWRs. The first project task was to develop representative nuclear fuel cycles and identify potential hazards and accident scenarios in the individual fuel cycle stages based on publicly available information. Because the nuclear fuel cycle is not established for any non-LWR concept, many assumptions were made, and it is anticipated that the details of the fuel cycles will eventually look different.Representative nuclear fuel cycles were developed for the pebble-bed high-temperature gas-cooled reactor (HTGR), the molten salt-fueled reactor (MSR), the pebble-bed fluoride salt-cooled high temperature reactor (FHR), the sodium-cooled fast reactor (SFR), and the heat pipe reactor (HPR). Publicly available specifications of representative reactor concepts served as basis for these fuel cycles. The discussion of each fuel cycle stage includes major occurring hazards, and a list of developed potential accident scenarios that is independent of the probability of these accidents to occur. Many of the fuel cycles have overlapping hazards and accident scenarios based on their coolant materials, fuel types, their shared need of UF 6 enrichment, transportation of UF 6 , and specific fuel type.

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Section: Fuel Pebble Transportationmentioning

confidence: 99%