Serial/Series Title

Month

Artificial Cooling of the Columbia River By Dam Regulation Part 1 (open access)

Artificial Cooling of the Columbia River By Dam Regulation Part 1

In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date: May 25, 1959
Creator: Kramer, H. A.
System: The UNT Digital Library
Hastelloy F Dissolver Installation in 321 Building (open access)

Hastelloy F Dissolver Installation in 321 Building

Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered during the fabrication of the vessels.
Date: May 25, 1959
Creator: Cooley, C. R.
System: The UNT Digital Library
Measurement of the Nuclear Materials Content of Non-Production Fuels (open access)

Measurement of the Nuclear Materials Content of Non-Production Fuels

In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date: May 25, 1959
Creator: Schneider, R. A.
System: The UNT Digital Library
Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices (open access)

Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices

The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solution of the transport equation such as the P1 and P3 solutions.
Date: May 25, 1959
Creator: Nilson, R. & Oakes, T. J.
System: The UNT Digital Library
Thermal Expansion of Pile Graphites (open access)

Thermal Expansion of Pile Graphites

Average coefficients of thermal expansion of the temperature range 25 C to approximately 425 C are reported for numerous types of graphite. The dependence of thermal expansion on crystal orientation and crystallite size and the effects of oxidation and cold test hole irradiation are discussed. An empirical relationship between thermal expansion and the initial rate of physical expansion under cold test hole irradiation is formulated.
Date: May 25, 1956
Creator: Riley, W. C. & Woodruff, E. M.
System: The UNT Digital Library