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Production test 221-T-18 scavenging of first-cycle waste

Description: The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.
Date: August 19, 1954
Creator: Schmidt, W.C. & Stedwell, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Probability of ruthenium reduction in H-4 by self-radiation

Description: The following calculations have been made at the request of H.R. Schmidt to determine the probability that self-radiation may play a substantial role in the decomposition of the ruthenium tetroxide in the reflux scrubber, section of the Redox Ruthenium Oxidizer (H-4). The validity of the derived data necessarily depends upon the correctness of the basic assumptions made with regard to process conditions and to possible radiation-activated mechanisms of disintegration. It is estimated that the e… more
Date: June 8, 1954
Creator: Upson, U. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria -- Reactor plant modifications for increased production and 100-C Area Alterations (Sections A and B) CG-558. Volume 1

Description: This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their ma… more
Date: August 10, 1954
Creator: Russ, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Monthly report of the Design Analysis Group for September 1954

Description: The following topics were discussed in this report: pressurization of the rear face for existing reactors; loss of steam in existing reactors; in-pile boiling in the 105-KER recirculation facilities; feasibility report for special study reactor plant; shielding requirements of the special study reactor plant; sulfuric acid addition to 100-K; radiation from activated iron in a recirculating system; ion exchanger activity from Fe corrosion; thermal shock-KER loop; shielding of tube bundles; adjus… more
Date: October 26, 1954
Creator: Andersen, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Sr{sup 90}, Sb{sup 125}, Cs{sup 137} and absolute beta activities in First Cycle Supernatent

Description: This report discusses procedures have been established for determining the absolute activities of Sr{sup 90}, Sb{sup 125}, Cs{sup 137}, and gross beta in First Cycle Supernatant. These procedures are also valid for other samples such as scavenged Radioactive Waste (RAW), the primary restriction being that the age of the material be at least 250 days so that any Sr{sup 89} activity (53 day half-life) is negligible. With the exception of the gross beta analysis the results are believed to be accu… more
Date: March 15, 1954
Creator: Helmholz, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separations Chemistry, Quarterly Progress Report, October-December 1953

Description: "Work has continued on high temperature methods for processing irradiated uranium fuel. Additional results have been obtained with fused halide treatment, solid scavengers and direct Pu distillation. With fussed fluorides about 95 per cent of the Pu was removed from a uranium sample, while treatment of uranium with HC1 gas removed almost all the Pu and many fission products. treatment of molten uranium with uranium oxide removed a substantial fraction of the fission products without removing P… more
Date: March 26, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MEETING XIV -- BEVATRON RESEARCH CONFERENCE -- CHEMISTRY EXPERIMENTS

Description: The main purpose of Chemistry Division personnel in using the Bevatron will be to learn as much as possible about nuclear reactions in the Bev energy range using the radiochemical approach. The type and extent of these experiments will depend greatly on the beam intensity. Significant results can be obtained at 10{sup 6} or 10{sup 7} protons per pulse, but it is highly desirable that this figure ultimately be raised to 10{sup 10} or greater.
Date: March 29, 1954
Creator: Hyde, Earl K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separations Chemistry Quarterly Progress Report for October-December 1953

Description: Work has continued on high temperature methods for processing irradiated U fuel. Additional results have been obtained with fused halide treatment, solid scavengers, and direct Pu distillation. With fused fluorides about 95% of the Pu was removed from a U sample,whiletreatment of U with HCl gas removed almost all the Pu and many fission products. Treatment of molten U with UO/sub 2/ removed a substantial fraction of the fission products without removing Fu. Uranium carbide treatment results wer… more
Date: March 26, 1954
Creator: Motta, E. E.; Bareis, D. W. & Cubicciotti, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Density, Viscosity, and Surface Tension of Light and Heavy Water Solutions of Uranyl Sulfate at Temperatures to 250 C. Final Report

Description: This report summarizes results of measurements of density, viscosity, and surface tension of light and heavy water solutions of uranyl sulfate at elevated temperatures, which measurements were made at Mound Laboratory for the Homogeneous Reactor Project at Oak Ridge National Laboratory.
Date: December 1, 1954
Creator: Barnett, M.K.; Heiks, J.R.; Jones, L.V. & Orban, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Notes Pertaining to Recuplex Product Evaporation

Description: A red-brown liquid formed during the evaporation of simulated Recuplex product solutions containing plutonium, nitric acid, carbon tetrachloride, and tributyl phosphate (TBP). The liquid is soluble in carbon tetrachloride. Concentration of solutions containing a TBP to plutonyl nitrate weight ratio of 0.15 or greater to a pot temperature of 150 deg C caused reactions which produced enough heat to bring the pot contents to a red heat with copious evolution of gases. Evaporation path curves and b… more
Date: April 28, 1954
Creator: Pugh, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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