Achievements in HAPO radiation monitoring, 1944--1954 (open access)

Achievements in HAPO radiation monitoring, 1944--1954

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.
Date: September 15, 1954
Creator: Unruh, C. M.; Selby, J. M. & Sanders, F. H.
System: The UNT Digital Library
THE FORMING OF ZIRCONIUM BY IMPACT EXTRUSION (open access)

THE FORMING OF ZIRCONIUM BY IMPACT EXTRUSION

None
Date: September 15, 1954
Creator: Rauch, W.G.
System: The UNT Digital Library
DEPOSITION OF SUSPENDED PARTICLES FROM TURBULENT GAS STREAMS. Technical Report No. 13 (open access)

DEPOSITION OF SUSPENDED PARTICLES FROM TURBULENT GAS STREAMS. Technical Report No. 13

None
Date: September 15, 1954
Creator: Friedlander, S.K.
System: The UNT Digital Library
A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power (open access)

A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)
Date: September 15, 1954
Creator: Weisner, E. F.
System: The UNT Digital Library