Document Details


Title:
Oak Ridge National Laboratory Status and Progress Report January 1955
Author(s):
Howard, F T [ORNL, Carbide and Carbon Chemicals Co., Oak Ridge]; Sullivan, W H [ORNL, Carbide and Carbon Chemicals Co., Oak Ridge]
Subject Terms:
biology, reactor, chemistry; homogeneous reactor, HRT; physics, chemistry, biology; progress report, ORNL; radioisotopes, ORR
Document Location:
DOE INFORMATION CENTER 1 Science.gov Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email: doeic@oro.doe.gov
Document Categories:
Science and Technology\Biology and Medicine; Specific Material\Uranium; Reactors\Research and Test Reactors and Small Experimental Piles
Document Type:
REPORT
Publication Date:
1955 Feb 04
Declassification Date:
1980 Jun 13
Declassification Status:
Declassified
Document Pages:
16
Accession Number:
ORF67127
Document Number(s):
ORNL 1849, Copy 160; Series A; SeriesA
Originating Research Org.:
Carbide and Carbon Chemicals Corporation
OpenNet Entry Date:
1998 Jun 16
Description/Abstract:
This document contains the Oak Ridge National Laboratory Status and Progress Report for January 1955. The Metal Recovery Plant was modified for use in recovering 75 tons of uranium and 10 kg of plutonium from reactor elements of the Brookhaven and the ORNL graphite reactors. A method was developed for stripping corrosion films from irradiated Zircaloy-2 pins which consisted of dehydrating the film by washing with acetone and air drying, followed by a cathodic treatment in 5 percent sulfuric acid. The design was completed for the nuclear sleeve through which the chamber for measuring reactor power will be inserted into the HRT shield. Preliminary design was started on a pilot plant to recover the ARE fuel by a fused salt--fluoride volatility process. Two major decisions made in December which required changes in the scheduling for the Oak Ridge Research Reactor project were: no contracts could be made until questions concerning hazard involved in operation were resolved; and the added investment required for an initial reactor power level of 20 Mw could be justified. There has been an acceleration in the production of Cesium-137 and the fabrication of pelleted cesium chloride sources for radiographic work, and an increase in the use of Iridium-192 for radiography. The main effort of the radioisotope development group is now on the design of the Multicurie Fission Products Pilot Plant. Studies on methods for remote control of the cesium alum crystallization process showed that a good indication of the start of crystallization can be obtained from a continuous recording of the temperature, and a definite temperature break is found at the start of crystallization. Considerable evidence is at hand to indicate that during the process of bacterial virus infection there is both a physical and a functional partition of the virus DNA and the virus protein. In the investigation of the "in vivo" effect produced after injection of mice with nucleoprotein from ascites tumor cells and their later challenge with tumor cells, two findings were: (1) mice showed no significantly altered mortality rate from that seen in the control unprepared ascites-challenged mice; and (2) marked differences in mortality rates with different dose levels. Radioisotope sales and costs, gross operating costs, and a personnel summary are included.


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