Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests (open access)

Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests

In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date: June 15, 1960
Creator: Bloomster, C. H.
System: The UNT Digital Library
Unique Fabrication Processes Applied to Fuel Cladding Materials (open access)

Unique Fabrication Processes Applied to Fuel Cladding Materials

The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date: March 15, 1960
Creator: Bush, S. H.
System: The UNT Digital Library
Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959 (open access)

Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959

One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date: June 15, 1960
Creator: Demmitt, T. F. & Wood, E. R.
System: The UNT Digital Library
Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube (open access)

Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube

The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.
Date: March 15, 1960
Creator: Hesson, G. M.
System: The UNT Digital Library
Ultrasonic Resin Level Detector (open access)

Ultrasonic Resin Level Detector

This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
System: The UNT Digital Library
Critical Mass Studies of Plutonium Solutions (open access)

Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System: The UNT Digital Library
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1 (open access)

Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date: March 15, 1960
Creator: Millhollen, M. K.
System: The UNT Digital Library
The Irradiated Rupture Prototype (IRP) Design (open access)

The Irradiated Rupture Prototype (IRP) Design

One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
System: The UNT Digital Library