Fringe isotope production (open access)

Fringe isotope production

The Purpose of the work described in this report has been to determine experimentally the rate of production of tritiun in fringe lithium-aluminum alloy loadings with the degree of precision necessary for economic analyses of such a method of isotope production. These results are provided for use in such an analysis.
Date: May 6, 1959
Creator: Bunch, W. L.
System: The UNT Digital Library
Hazards Summary Report for the Walter Reed Army Medical Center Nuclear Research Reactor (open access)

Hazards Summary Report for the Walter Reed Army Medical Center Nuclear Research Reactor

Detailed descriptions are given concerning the reactor design, operation, location, and the using agency. Potential hazards are evaluated along with safeguards. A supplement is included which further describes the reactor core. (J.R.D.)
Date: May 6, 1959
Creator: Cappel, H.H.
System: The UNT Digital Library
Interim report on laboratory experiments investigating consequences of failure of front hydraulic fittings in ``C`` OCD geometry (open access)

Interim report on laboratory experiments investigating consequences of failure of front hydraulic fittings in ``C`` OCD geometry

None
Date: May 6, 1959
Creator: Fitzsimmons, D. E. & Hesson, G. M.
System: The UNT Digital Library
Evidence for Subshell at N = 152 (open access)

Evidence for Subshell at N = 152

None
Date: May 6, 1954
Creator: Ghiorso, A.; Thompson, S. G.; Higgins, G. H.; Harvey, B. G. & Seaborg, G. T.
System: The UNT Digital Library
Safety Experience: Reactor and Critical Facilities (open access)

Safety Experience: Reactor and Critical Facilities

This document provides a discussion of reactor safety of the Hanford production reactor and critical facilities. A description of each facility is provided and details of significant safety incidents are provided.
Date: May 6, 1955
Creator: Greager, O. H.
System: The UNT Digital Library
Definitive process design, Redox multi-purpose dissolver installation (open access)

Definitive process design, Redox multi-purpose dissolver installation

This document provides the required definitive scope design for dissolver equipment capable of nuclear safe processing by geometry of E-Metal and certain other fuels enriched to a maximum of one per cent U-235 equivalent. Using only a single dissolver installation of this design, it will be possible to process the current E-Metal monthly commitment in less than two weeks (five-day week). The proposed dissolver system is to incorporate design flexibility required to permit conversion to Zirflex processing of NPR fuels.
Date: May 6, 1959
Creator: Gustafson, L. D.
System: The UNT Digital Library
Nuclear Testing and Flash Blindness (open access)

Nuclear Testing and Flash Blindness

None
Date: May 6, 1958
Creator: Merritt, M. L.
System: The UNT Digital Library
DENSITIES AND BOILING POINTS OF URANYL NITRATE-NITRIC ACID SOLUTIONS (open access)

DENSITIES AND BOILING POINTS OF URANYL NITRATE-NITRIC ACID SOLUTIONS

The intercycle evaporators in the Chemical Processing Plant are controlled by density-measuring instruments. Because of difficulties in controlling these evaporators in a satisfactory manner, a series of investigations was begun to measure the boiling points at the elevation of the CPP, and densities near boiling temperatures of a number of solutions in the uranyl nitrate-nitric acid-water system. From these data it was hoped to evaluate temperature sensitve devices as controllers for the evaporators.
Date: May 6, 1953
Creator: Perkins, R.H.
System: The UNT Digital Library