Idaho National Engineering Laboratory

• Absolute thermal fission yields for p235sU
• Actinide partitioning from ICPP waste
• An assessment of hydrogen generation for the PBF severe fuel damage scoping and 1-1 test
• COMCAN II, a computer program for common failure analysis
• Fast reactor fission yields for p240sPu and p242sPu
• Fast reactor fission yields for Pu and Pu
• Isotope correlation studies relative to high enrichment test reactor fuels
• Measurement and control techniques in geothermal power plants
• Methods evaluation for the continuous monitoring of carbon-14, krypton-85, and iodine-129 in nuclear fuel reprocessing and waste solidification facility off-gas
• Pipe damping
• Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October-December 1980
• Reactivity initiated accident test series test RIA 1-2 fuel behavior report