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Search U.S. government technical reports digitized or harvested by TRAIL.
Keyword Search
3 results returnedPublished Year
Subject
- Neutron flux (3) *
- FORTRAN IV (Computer program language) (1)
- Neutron tranport theory (1)
- Neutron transport theory (1)
- Nuclear fission--Measurement (1)
- Nuclear fuel rods--Thermal properties (1)
- Nuclear reactors--Computer programs (1)
- Nuclear reactors--Mathematical models (1)
- Nuclear reactors--Measurement (1)
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