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Hanford Engineering Development Laboratory.

  • Core engineeringCore engineering
  • Densification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiationDensification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiation
  • Densification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiationDensification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiation
  • Densification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiationDensification-induced strains in 20% cold-worked 316 stainless steel during neutron irradiation
  • DNDDND
  • HEDL magnetic fusion energy programs progress reportHEDL magnetic fusion energy programs progress report
  • Maximum allowable temperature for storage of spent nuclear reactor fuelMaximum allowable temperature for storage of spent nuclear reactor fuel
  • Thermal effects of projected power growth: north Atlantic river basinsThermal effects of projected power growth: north Atlantic river basins