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Technical Report Archive and Image Library
83
TRAIL Microcard Collection
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Technical Report Archive and Image Library
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TRAIL Microcard Collection
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Argonne National Laboratory Reports
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Argonne National Laboratory Reports
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Advanced Fuel Cell Development Progress Report
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Fuel Cycle Programs Quarterly Progress Report
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Plutonium Calorimetry and SNM Holdup Measurements Progress Report
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Practical Superconductor Development for Electrical Power Applications Annual Report
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Speciation of Radionuclides in Natural Groundwaters Annual Report
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Argonne National Laboratory Reports
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Final Summary Report of Fuel-Dynamics Tests H2 and E4
Analytical Investigation of Certain Aspects of LMFBR Subassembly-Failure Propagation
Chemical Technology Division Annual Technical Report for 1984
An Alternative Library Under 4. 2 BSD UNIX on a VAX 11/780
Analysis of Heat-Pipe Absorbers in Evacuated-Tube Solar Collectors
Heat Extraction from the ANL Research Salt Gradient Solar Pond
Decontamination and Decommissioning of the Argonne National Laboratory Building 350 Plutonium Fabrication Facility : Final Report
The Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment: Part 1, SRL 165 Glass
Transforming Fortran DO Loops to Improve Performance on Vector Architectures
Effect of Depth of Discharge on Lead-Acid Battery Overcharge Requirements
Magnetically Confined Kinetic-Energy Storage Ring: a New Fundamental Energy-Storage Concept
Branching Fraction in the Radioactive Decay of ⁸⁵mKr
The Delayed-Neutron Fraction in a Pulsed Spallation Neutron Source
Fast Critical Assembly Safeguards Summary Report, October 1978 - September 1979, Volume 1
Fuel Cycle Programs, Quarterly Progress Report: April-June 1980
Advanced Fuel Cell Development Progress Report: April-June 1983
Tube Vibration in Industrial-Size Test Heat Exchanger (90° Square Layout)
Experiments on Tubes Conveying Fluid
Natural Thermal Stratification in Tanks : Phase 1 Final Report
Canonicalization and Demodulation
Effects of Curvature on Asymmetric Steady States in Catalyst Particles
ICECO-CEL: A Coupled Eulerian-Lagrangian Code for Analyzing Primary System Response in Fast Reactors
The Application of Neutron-Activation Analysis to the Determination of Leach Rates of Simulated Nuclear-Waste Forms
COMMIX-PPC: A Three-Dimensional Transient Multicomponent Computer Program for Analyzing Performance of Power Plant Condensers, Volume 1: Equations and Numerics
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