Access
Resource Type
Partner
Collection
Technical Report Archive and Image Library
1,311
National Advisory Committee for Aeronautics Collection
806
Office of Scientific & Technical Information Technical Reports
468
TRAIL Microcard Collection
267
Harris and Eliza Kempner
164
Government Documents General Collection
10
John F. Kennedy Memorial Collection
4
John F. Kennedy, Dallas Police Department Collection
4
Texas State Publications
3
Stillwater History Museum at the Sheerar, Stillwater, Oklahoma
2
5 More
Serial/Series Title
NACA Research Memorandums
523
NACA Technical Notes
228
Atomic Energy Commission Reports
168
Personal Papers (MS 80-0002)
164
United States Geological Survey Reports
136
Trace elements investigations report
104
University of California Radiation Laboratory Reports
51
NACA Technical Reports
43
Los Alamos National Laboratory Reports
34
Imperial Sugar Company Estimated Daily Cash Balance
32
92 More
States
1,967 Matching Results
Results open in a new window/tab.
Nitric acid recovery and ammonia removal: Modifications to the Redox dissolver off-gas systems
Project CG-588 authorized the design and construction of dissolver and waste neutralizer off-gas scrubbers to remove the ammonia given off during coating removal and waste neutralization steps of the Redox operation. It has always been recognized that the nitrogen oxides in the dissolver off-gases, resulting from the dissolution of bare uranium slugs, could also be absorbed in water under proper conditions to give re-useable nitric acid. Consequently it appeared feasible to provide facilities which would combine these ammonia removal and nitric acid recovery operations. The purpose of this report is to present a scope design for the economical recovery of nitric acid from the Redox dissolver off-gases in addition to the removal of ammonia. It is recognized that acceptance of this scope for project execution would make unnecessary the ammonia scrubbers for the dissolver off-gases of Project CG-588. 8 refs.
Date:
October 1, 1954
Creator:
Stoker, D. J.
System:
The UNT Digital Library
Uranium in the Black Rock District Yavapai County, Arizona
From abstract: A radioactivity survey of the Black Rock district in southern Yavapai County, Ariz, disclosed anomalous radioactivity in several localities, chiefly at the Abe Lincoln mine in sec. 11, T. 8 N., R. 3 W., about 14 road miles northeast of Wickenburg. The Abe Lincoln vein system occupies a fault zone which strikes N. 500 E. and dips from 780 to 870 NW. Moderate radioactivity is present at the Bracken property and at several other localities in the Black Rock district. The writers recommend re-opening the Abe Lincoln mine to permit a more extensive examination of the vein.
Date:
April 1954
Creator:
Haines, D. V. & Raup, Robert B., Jr.
System:
The UNT Digital Library
Sampling SX-tank farm condensate
In accordance with the policy that a centralized inventory shall be kept of all radioactive waste liquid discharged to ground, it is recommended that the volumes of condensate from the SX-farm, the dates or periods of discharge, and the activity densities of radioisotopes in the condensate discharged be determined by Separations Section and reported regularly to the Radiological Standards Unit. This paper is a description of the condensate system, with recommendations for sampling and analysis.
Date:
May 7, 1954
Creator:
Clukey, H. V.
System:
The UNT Digital Library
Disposal of irradiated waste Ink'' solution (Production Test 105-529-A)
Boron solution circulated through special poison tubes to achieve more variable control of neutron flattening'' was tested in the 100-DR Hanford reactor. About 2700 gallons of irradiated waste Ink solution from Production Test 105-529-A was discharged to an underground crib at 100-DR, after radiochemical analyses and evaluation of radiation protection aspects by the Radiological Sciences Department. In case the Ink method is considered for production use at Hanford in the future, further biological and biophysical study is recommended to determine whether irradiated waste Ink solution may be disposed of into the Columbia River, into the ground near the river, or into the ground several miles from the river. 10 refs, 2 tabs.
Date:
July 20, 1954
Creator:
Clukey, H. V.
System:
The UNT Digital Library
Slug and tube factors
A common and useful assumption is that the front-to-rear power distribution is a shortened cosine curve. This fact led to the calculation of slug factors'' for the longer charges to be used at K-Pile. It is hoped that the publication of these numbers will save time and prevent duplication of effort by those concerned in any way with slug power, surface temperatures, reactivity effects, etc. For the sake of completeness, slug factors for the older piles are included. Another useful ideal is that tube power distributions can be approximated by the assumption of a cylindrical pile and a cosine distribution of power outside of a central flattened region. This led to another double set of numbers since the values for the 2004 tube piles were again included for completeness. 2 figs., 6 tabs.
Date:
May 13, 1954
Creator:
Moon, M.R. & Brugge, R.O.
System:
The UNT Digital Library
Tube power distribution at start-up of 105-KW
None
Date:
April 2, 1954
Creator:
Foster, L.E.
System:
The UNT Digital Library
Design considerations regarding slug ruptures in the intermediate power level reactor
The minimum shutdown time, to permit accessibility, for the Intermediate Power Reactor is estimated to be 38 hours. In case the reactor were shutdown following each rupture this long shutdown period would have serious disadvantages. The desirability of being able to make firm power commitments (independent of slug ruptures) has led to a study of the possibility of continuous operation following a rupture. There is evidence to indicate that, at the proposed water temperature, the rate of corrosion of uranium may be so high that at least a major portion of the rupture products may have entered the system before the reactor can be shutdown. A pushout of the affected column would then be a pushout of only those slugs which are still intact and the problem would still remain of removing the rupture products from the system. The first portion of this report is concerned with the rate of corrosion of a slug following rupture and the possible limitations to the principle of non-shutdown operation. These limitations include a flow stoppage by the ruptured can, undue increase in gamma activity, increased corrosion by the rupture products, and adherence of rupture products to the piping. The latter portion of the …
Date:
November 1, 1954
Creator:
Pearl, W. L. & Pursel, C. A.
System:
The UNT Digital Library
Production test 221-T-18 scavenging of first-cycle waste
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.
System:
The UNT Digital Library
Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals
Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]
Date:
June 25, 1954
Creator:
Harrison, William B.
System:
The UNT Digital Library
Age Calculations for Lattices with Aluminum-Matrix Slugs
The process of age calculation for Hanford exponential lattices containing aluminum-matrix slugs, where the sums run over the materials of the lattice cell.
Date:
June 8, 1954
Creator:
Neumann, Herschel
System:
The UNT Digital Library
Probability of ruthenium reduction in H-4 by self-radiation
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 extent of solid ruthenium formation in the tower which results from radiation effects should not exceed 100 micrograms per batch. This rate is negligible compared to that now found in the presence of stainless steel packing, or to that which might be expected from thermally-activated disintegrations alone.
Date:
June 8, 1954
Creator:
Upson, U. L.
System:
The UNT Digital Library
Discussion of ruthenium problem in Redox Plant
A meeting was held February 5, 1954 in the 2704-Z Building to discuss the ruthenium problem in the Redox Plant and to decide on a course of action to correct the problem. The following persons were in attendance.
Date:
February 8, 1954
Creator:
Mobley, W. N.
System:
The UNT Digital Library
BiPO{sub 4} plant nickel ferrocyanide scavenging flowsheet for first-cycle waste containing no coating-removal waste
Management of first-cycle wastes from the Bismuth Phosphate Plant using Nickel Ferrocyanide scavenging is described.
Date:
September 30, 1954
Creator:
Coppinger, E. A. & Smith, R. E.
System:
The UNT Digital Library
Process Test MR-105-23 cathodic protection of the 107-C retention basins
This report provides details of a test to determine the feasibility of preventing corrosion of the 107- C retention basins by the installation of a small scale cathodic protection system.
Date:
July 12, 1954
Creator:
Bloomstrand, R. R.
System:
The UNT Digital Library
Essential material flow sheet of precipitation separations process
This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, and Second Decontamination Cycle through the Lanthanum Fluoride Product Precipitation volumes at 49% of this standard.
Date:
August 19, 1954
Creator:
Browne, W. G. & Murray, H. W.
System:
The UNT Digital Library
Production test 105-576-A: Irradiation of powder metal compact slugs
The purpose the production test described in this document was to evaluate by pile irradiation the stability and resistance to rupture of powdered metal compacts.
Date:
July 1, 1954
Creator:
Reid, R. W.
System:
The UNT Digital Library
Nickel ferricyanide scavenging flowsheet for neutralized concentrated raw
From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is possible by scavenging these wastes. In this document, a chemical flowsheet is presented for use as a design basis of facilities which will permit scavenging of these stored wastes.
Date:
October 26, 1954
Creator:
Smith, R. E. & Coppinger, E. A.
System:
The UNT Digital Library
The Rf System of the Bevatron
Report discussing details of the design for the Bevatron at the University of California Radiation Laboratory. The Bevatron is a "6-billion-electron-volt (Bev) proton synchotron. This device will receive a 10-million-electron-volt (Mev) proton beam from a linear accelerator, and further accelerate a reasonable percentage of these protons, at a nominally constant radius of 600 inches, to a final energy greater than 6 Bev."
Date:
June 4, 1954
Creator:
Winningstad, C. Norman
System:
The UNT Digital Library
Factors Influening Ammonia Decomposition in the Kjeldahl Method with Sealed Tube Digestion
This report follows the work on the Kjedahl digestion procedure in sealed tubes at 470 C. as well as analyzing factors influencing ammonia decomposition within these tubes.
Date:
June 1954
Creator:
Green, LeRoy G.; Koch, Charles William; Grunbaum, Benjamin W. & Kirk, Paul Leland, {}
System:
The UNT Digital Library
Summary of Recent External Neutron-Yield Measurements by the MnSO₄ Tank Method
Report that summarizes unreported neutron-yield data for the MnSO₄ tank method. Other yield measurements had been reported in other quarterly reports prior to the completion of this one.
Date:
September 17, 1954
Creator:
Crandall, Walter E. & Millburn, George P.
System:
The UNT Digital Library
Neutron Production by High-Energy Particles
Abstract: "From neutron-yield measurements made with a MnSO4 detecting solution, the average number of neutrons produced per inelastic event is determined for a series of elements from lithium to uranium for 340-Mev protons, 190-and 315-Mev deuterons, 490-Mev He3 ions, and 90- and 160-Mev neutrons. The results are analyzed in an attempt to understand the total yield measurements for thick targets and to explain the variation of yield with the atomic number of the target."
Date:
September 29, 1954
Creator:
Crandall, Walter E. & Millburn, George P.
System:
The UNT Digital Library
Use of Controlled Photosynthesis for Maintenance of Gaseous Environment
Abstract: "The problem of maintaining livable oxygen and carbon dioxide pressures in a closed space in which men must live leads to consideration of the possible use of the photosynthesis of green algae. A calculation based on the known respiratory rate of man and the photosynthetic rates of Chlorella indicates that it would be feasible to use algae for this purpose."
Date:
September 1954
Creator:
Bassham, James Alan
System:
The UNT Digital Library
Effects of Ionizing Radiation on Choline Chloride and Its Analogs
Abstract: "Choline chloride and six analogs have been exposed in the dry, crystalline state to high-energy electron and gamma radiation. This investigation has confirmation the abnormal radiation sensitivity of choline chloride. Its G values (molecules decomposed/100 ev) were found to be: e- -radiation, 20; y-radiation, 175. These high values indicate a chain mechanism for the solid-state reaction. The G values for the choline analogs were found to range from 1 to 18 for the electron irradiations and from 1 to 32 for the gamma irradiations. Betaine hydrochloride approaches choline chloride in instability toward high-energy electrons but is far more stable in the presence of y-rays."
Date:
December 1954
Creator:
Lemmon, Richard M.; Parsons, Margaret A. & Chin, Doris M.
System:
The UNT Digital Library