Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964 (open access)

Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.
Date: April 27, 1965
Creator: unknown
System: The UNT Digital Library
Heat Transfer Study for Self-Boiling Radioactive Wastes (open access)

Heat Transfer Study for Self-Boiling Radioactive Wastes

The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding soil.
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
System: The UNT Digital Library
Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹ (open access)

Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹

Calculations are presented regarding the effect of delayed neutrons in reactors fueled with mixtures of Pu²³⁹ and U²³⁵. Results are plotted to illustrate the change in thermal flux as a function of time for various positive or negative step changes in reactivity.
Date: April 27, 1956
Creator: Astley, E. R.
System: The UNT Digital Library
Carbon Steel Program for High Temperature Reactor Systems (open access)

Carbon Steel Program for High Temperature Reactor Systems

The Reactor Design and Development Unit has just completed a design concept for an intermediate capacity dual purpose reactor plant utilizing carbon steel for the primary loop portion outside the reactor. This design concept is reported in HW-33157 AD (2). The economic and engineering gains are of sufficient magnitude to justify an accelerated and extensive test program to completely evaluate the remaining unknowns in utilizing carbon steel as a stainless steel substitute. It is the purpose of this document to up-date and elaborate the information contained in the two previous documents (1). . It is the further purpose to define the program required to implement the design concept developed by the Reactor Design and Development Unit (2) utilizing carbon steel as the primary loop structural material.
Date: April 27, 1955
Creator: Pearl, W. L.
System: The UNT Digital Library
Potential Nitrate Decomposition High Level Waste Storage (open access)

Potential Nitrate Decomposition High Level Waste Storage

It is recommended that self-concentration of Purex wastes should not be started until much more complete knowledge is obtained of the conditions and reactions in these wastes. The presently planned tests in the Semi-Works will be a practical demonstration of the problems but will be of little value on the initial Purex wastes as these tests are being run almost concurrent with the filling of the first Purex storage tank.
Date: April 27, 1955
Creator: Anderson, C. R.
System: The UNT Digital Library