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Plutonium Oxide- Plastic Mixtures for Critical Mass Studies (open access)

Plutonium Oxide- Plastic Mixtures for Critical Mass Studies

Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date: May 12, 1960
Creator: Crocker, H. W.
System: The UNT Digital Library
Completion Report An Automatic Fuel Element Stamping Machine (open access)

Completion Report An Automatic Fuel Element Stamping Machine

This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
System: The UNT Digital Library
Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959 (open access)

Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the disposition of contaminated major processing equipment at Hanford Atomic Products Operation during 1958-1959 and a listing of 1) equipment buried, 2) equipment stored, to be buried or decontaminated, and 3) equipment decontaminated and returned to service.
Date: February 12, 1960
Creator: Kingsley, P. S.
System: The UNT Digital Library
Once Through Decontamination Studies- Interim Report No. 1. (open access)

Once Through Decontamination Studies- Interim Report No. 1.

The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has also been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This report contains information on a series of tests performed in the 242-B single pass flow facility. Information concerning the following are presented: (1) Efficiency of decontaminating KER Loop 1 and 2 contaminated specimens. (2) Efficiency of decontaminating present reactor pigtails by different methods. (3) Areas that need further study.
Date: January 12, 1960
Creator: Perrigo, L. D. & Hekenson, J. F.
System: The UNT Digital Library
Final Report of Piping Components for Organic Coolants (open access)

Final Report of Piping Components for Organic Coolants

Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This report will cover final results and other pertinent information.
Date: January 12, 1960
Creator: Floyd, H. L.
System: The UNT Digital Library
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C (open access)

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
System: The UNT Digital Library
PRTR Calandria Fabrication Report (open access)

PRTR Calandria Fabrication Report

The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and lists recommendations for improving the design and reducing the cost.
Date: July 12, 1960
Creator: Pedersen, L. T. & Kreiter, M. R.
System: The UNT Digital Library
Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple (open access)

Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
System: The UNT Digital Library