Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model (open access)

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
System: The UNT Digital Library
6144-Channel Time-of-Flight Analyzer (open access)

6144-Channel Time-of-Flight Analyzer

Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
System: The UNT Digital Library
Analog Computer Simulation of a Pulsed Extraction Column (open access)

Analog Computer Simulation of a Pulsed Extraction Column

Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
System: The UNT Digital Library
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies (open access)

Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960 (open access)

Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: September, 1959 Through August, 1960

Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date: September 16, 1960
Creator: Scott, P. A.
System: The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
System: The UNT Digital Library
Thermal Conductivity of UO2 (open access)

Thermal Conductivity of UO2

Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
System: The UNT Digital Library
Surface Dosimetry and Effective Energy Calculations (open access)

Surface Dosimetry and Effective Energy Calculations

Methods of the Radiation Monitoring Operation of the Chemical Processing Department.
Date: September 8, 1956
Creator: Helgeson, G. L.
System: The UNT Digital Library
Portable Radiation Survey Instrument (open access)

Portable Radiation Survey Instrument

Report describing a portable radiation survey instrument, its design, and usage.
Date: September 1963
Creator: Sheen, E. M. & Spear, W. G.
System: The UNT Digital Library
The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2 (open access)

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
System: The UNT Digital Library