Resource Type
Serial/Series Title
Evaluation of Roof Bolting Requirements Based on In-Mine Bolter Drilling Progress Report
5
Hanford Laboratories Operation Monthly Activities Report
3
Fiscal Year 2003
2
Low-Cost Solar Array Project
2
A Development of On-Line Temperature Measurement Instrumentation for Gasification Process Control Progress Report
1
ANL Reactor Development Program Progress Report
1
Develop Data Management System for Assistance in Conducting Area of Reviews in Texas Quarterly Report
1
Fiscal Year 1983
1
Fiscal Year 2002
1
Fiscal Year 2004
1
10 More
Decade
Month
Day
Language
531 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
531
next
The Fission of Thorium with Alpha Particles
The fission distribution of fission of thorium with alpha particle of average energy 37.5 Mev has been measured by the chemical method. The distribution found shows that the characteristic dip in the fission yield mass spectrum has been raised to within a factor of two of the peaks compared to a factor of 600 in slow neutron fission of U{sup 235}. The raise in the deip has caused a corresponding lowering in fission yield of these elements at the peaks. The cross section for fission of thorium with 37.5 Mev alphas was found to be about 0.6 barn, and the threshold for fission was found to be 23 to 24 Mev.
Date:
April 15, 1948
Creator:
Newton, Amos S.
Object Type:
Article
System:
The UNT Digital Library
[Office of Hanford Directed Operations events of importance for week ending April 13, 1949]
This report details events of importance reported by the Hanford Operations Office for the week ending April 13, 1949.
Date:
April 15, 1949
Creator:
Schlemmer, F. C.
Object Type:
Report
System:
The UNT Digital Library
The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery
A study was made of the stability of tributyl phosphate (TBP) to acids, bases, and UO/sub 2/(NO/sub 3/su)/sub 2/ solutions, and of the chemistry of its decomposition products. The effect of such decomposition products on the extraction behavior of ion of MBP and lines the RAW analyzer and a subsequent reduction of feed flow rate in each case resulted in immediate reduction in losses, as evidenced by the polarographic results. In many such instances, several hours of operation at high waste losses were avoided. A dropping mercury electrode was used for stream analysis, and the RAW solution was analyzed directiy without either dilution or addition of supporting eleclrolyte. Removal of dissolved oxygen and control of temperature were urnecessary. The precision of the method was better than plus or minus 5%, and the accuracy, which is dependent on calibration with a standard solution, was well within the precision value. The calibration curve is linear, for practical purposes, up to approximately 8 g/l UNH or 0.032 lb/gal uranium. (auth)
Date:
April 15, 1951
Creator:
Wagner, R. M.
Object Type:
Report
System:
The UNT Digital Library
ALTERNATE VALVE STUDIES
None
Date:
April 15, 1952
Creator:
McLean, H.J. & Wirta, R.W.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of etchants for deoxidizing aluminum components
In the canning operation, the preparation of aluminum components is important in assuring uniform wetting of the aluminum surfaces with Al-Si. The surfaces of the components should be free of dirt and grease and should also have a minimum retention of non-metallic film, normally aluminum oxide, for the best wetting properties. At present, dirt and grease are removed satisfactorily by a vapor degreaser followed by a Duponol-alkaline wash. The standard specified method of removing the aluminum oxide film from aluminum cans is a four-minute etch in twenty percent phosphoric acid. The oxide is removed from the caps by an eight-minute etch in twenty per cent phosphoric acid or an alternate etch of a one percent solution of hydrofluosilicic acid. If the phosphoric acid etch is not controlled properly, it is possible to form a thin, inert phosphate coating on the surface of the aluminum, which is undesirable for good wetting characteristics. In an effort to find a better etchant for aluminum components, an investigation of various commercial and non-commercial etchants was undertaken. This report details results of this investigation.
Date:
April 15, 1953
Creator:
Weakly, E. A.
Object Type:
Report
System:
The UNT Digital Library
Problems of Refining Uraniferous Residues. Progress Report for March 1953
None
Date:
April 15, 1953
Creator:
Fleck, H. & Summers, J. E.
Object Type:
Report
System:
The UNT Digital Library
Quadrupole Focusing Lenses for Charged Particles
A set of four strong focusing magnetic quadrupole lenses has been constructed and operated. Each lens consists of four air cooled electromagnets with pole tips having a hyperbolic cross section. Each lens is 4 in. long and has an aperture 2 in. in diameter. Measurements of the magnetic field demonstrate that the hyperbolic cross section satisfies the requirements of a constant magnetic field gradient very well. The technique of deflecting a current carrying flexible wire has been used to measure the trajectory of charged particles through the system of lenses. It has been observed that the strong focusing requirements are satisfied. The system of lenses was then used to focus 0.5 Mev protons, 20 Mev deuterons, and 40 Mev alpha particles. The parallel beam of 0.5 Mev protons was detected by observing the incandescence of a quartz plate while the protons were bombarding it. The focused beam was less than 1 mm in diameter. The astigmatic 20 Mev deuteron beam from the 60 in. cyclotron was increased in current density by a factor greater than 30.
Date:
April 15, 1953
Creator:
Cork, Bruce & Zajec, Emery
Object Type:
Report
System:
The UNT Digital Library
The Plutonium Feedback Approach to Nuclear Power
Nuclear parameter variations are presented for sodium graphite reactors using Pu-spiked natural U as fuel. The fuel feed is assumed to be natural U, and the important variables are the initial amount of excess reactivity, lattice spacing, and alpha , the ratio of Pu/sup 239/ to U/sup 235/ in the feed material. The system is called "steady state" in that the ratios, N/sub 40/N/sub 49/ = sigma /sub c(49)// sigma /sub a(40)/ and N/sub 41//N/sub 4 9/ = sigma /sub c(49)/ / sigma /sub a(41)/, obtained from setting the build-up equations to zero are assumed for the feed concentrations, and the feed material to the reactor is always the same. During irradiation, the U/sup 235/ and U/sup 238/ concentrations steadily decline while the Pu isotope concentrations initially increase, then decline. To ensure sufficient plutonium for feed material, it is necessary to remove the fuel from the reactor before the Pu content drops below its initial value. Although the reactivity variations presented were calculated specifically for sodium graphite reactors, they may be applied to any thermal reactor using Pu-spiked natural U as fuel. The reactivity changes are determined primarily by the fuel characteristics and are only slightly dependent on the other …
Date:
April 15, 1955
Creator:
Roderick, C.
Object Type:
Report
System:
The UNT Digital Library
REACTOR ENGINEERING DIVISION QUARTERLY REPORT ON THE POWER REACTOR PROGRAM FOR JANUARY 1, 1955 THROUGH MARCH 31, 1955
None
Date:
April 15, 1955
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
REACTOR ENGINEERING DIVISION UNCLASSIFIED QUARTERLY REPORT FOR JANUARY 1, 1955 THROUGH MARCH 31, 1955
None
Date:
April 15, 1955
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Study of the Reaction of Metals and Water. Interim Report
None
Date:
April 15, 1955
Creator:
Higgins, H. M.
Object Type:
Report
System:
The UNT Digital Library
Sodium Graphite Reactor Quarterly Progress Report for October-December 1955. Section A. Section B
An analysis was made of the nuclear parameters for sodium graphite reactor lattices. These parameters include thermal utilization, macroscopic cross sections, thermal diffusion length, and neutron absorption. Results of all calculations are given in graphical form. Test fuel slugs for the SRE were cycled up to 500 times between 100 and 500 deg C at the rate of 2 cycles/hr. Results are tabulated. The centrifugal casting of U alloy fuel slugs is briefly evaluated. Results of the microscopic examination of the extruded ThU breeder fuels are shown. The percent elongation of graphite due to the presence of Na is shown for various temperatures. Results of wear tests on graphite are also tabulated. The behavior of Zr in liquid Na was studied, and weight gains in Zr are summarized. Analog computer studies were continued, and data are included on the temperature effects of the response time of coolant channel Na outlet temperature thermocouples, the effects of continuous rod motion and pump speed changes on the outlet Na temperature and power, and the outlet temperature as a function of scram time. The critical evaluation of B--Ni rods is tabulated. The fuel rod assembly apparatus is described. Fuel rod development is discussed. Cyclograph …
Date:
April 15, 1956
Creator:
Martin, A. B. & Cochran, J. C.
Object Type:
Report
System:
The UNT Digital Library
Diffusion of Uranium and Aluminum-Silicon Eutectic Alloy
None
Date:
April 15, 1957
Creator:
Green, D. R.
Object Type:
Report
System:
The UNT Digital Library
Enrichment of Isotopes by the Difference in Rates of Isotopic Reactions
The difference in rates of reaction of isotopic molecules may be utilized to produce appreciable isotope enrichments. When a competitive irreversible isotopic reaction is carried out to a high extent of completion, the residual unconverted substrate becomes exponentlally enriched in the heavier isotope. In deuterium systems, a substantial function of the D inventory is retained in the enriched residual substrate, so that conversion of the depleted product is unnecessary. For isotopes of heavier elements such as C/sup 13/, N/ sup 15/, and O/sup 18/ the retention is low, so that product conversion and recycling is desirable unless the starting material is of negligible value. Experiments are described in which enrichments of C/sup 13/ have been obtained using the reaction rate principle in dehydration of formic acid and hydrolysis of urea. Procedures are given for the preparation of decimolar barium carbonate at the level of 1.6% C/sup 13/, and molar barium carbonate at the 1.4% level starting with commercial materials. (J.R.D.)
Date:
April 15, 1957
Creator:
Bernstein, R. B.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: March 1957
This is the monthly report of the Hanford Laboratories Operation, March, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date:
April 15, 1957
Creator:
Albaugh, E. W.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Results on the Kinetic Behavior of Water Boiler Reactors
None
Date:
April 15, 1957
Creator:
Hetrick, D. L.; Flora, J. W.; Gardner, E. L.; Moskowitz, B. R.; Muller, D. R.; Remley, M. E. et al.
Object Type:
Report
System:
The UNT Digital Library
A STUDY OF THE PRIMARY SHIELD FOR THE PRDC REACTOR
Temperature distributions, irradiation effects, stacking arrangements, voidage, and economics for the borated-graphite shield of the PRDC reactor were investigated. Of the shield systems considered, four are reported here. System 1 contalns 30 in. of 1% borated graphite, with either ordinary graphite or a cement as a filler for the remaindcr of the volume. The maximum temperature at the flex plates in this system was calculated to be 5OO deg F. Systems 2 and 3 consist of 2 in. of 5% borated graphite near the core vessel and 1/2 in. of Boral at the primary-shield tank. A filler material of carbon blocks is used in System 2 and graphite in System 3. The calculated maximum temperatures were 700 deg F and 35O deg F, respectively. System 4 consists of a laminated structure of Boral and graphite near the primary-shield tank and carbon-block filler. It was calculated to have a maximum temperature of 600 deg F at the flex plates. The maximum temperature at the flex plates recommended by APDA is 500 deg F. Energy storage and radiation damage were found to be within permissible limits in all four systems. However, these conclusions are based on experimental data from the Hanford reactor …
Date:
April 15, 1957
Creator:
Epstein, H.M.; Dingee, D.A. & Chastain, J.W.
Object Type:
Report
System:
The UNT Digital Library
A CALCULATION OF THE ENERGY SPECTRUM AND ANGULAR DISTRIBUTION OF GAMMA RAYS AT THE SURFACE OF THE BSF REACTOR
The energy and angular distributions of the gamma rays leaking from the BSF reactor were computed by (((((((((Abstract unscannable))))))))))
Date:
April 15, 1958
Creator:
Bowman, L. A.; Dunn, W. W.; Lessig, R. H. & Trubey, D. K.
Object Type:
Report
System:
The UNT Digital Library
Engineering Study on Underground Construction of Nuclear Power Reactors
The advantages, disadvantages, and cost of constructing a auclear power reactor underground are outlinedData on underground construction of hydroelectric plants, other structures, and underground reactor projects in Norway and Sweden are reviewed. A hypothetical underground Experimental Boiling Water Reactor design and sketch are given with cost estimates(T.R.H.)
Date:
April 15, 1958
Creator:
Beck, C.
Object Type:
Report
System:
The UNT Digital Library
Fuels Preparation Department monthly report for March 1958
This document details activities of the Fuels Preparation Department during the month of March 1958.
Date:
April 15, 1958
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: March 1958
This is the monthly report for the Hanford Laboratories Operation, March, 1958. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date:
April 15, 1958
Creator:
Hanford Laboratories
Object Type:
Report
System:
The UNT Digital Library
HIGH-FLUX REACTOR--MACHINE CALCULATION
By means of 2-group, 3-region calculations the following features are investigated for a flux-trap reactor: finite fuel-layer thickness, moderation in the fuel layer, diffusion constant of the fuel layer, reflector thickness, and flux-trap radius. A 31-group calculation was used to study simultaneously finite fuel-layer thickness, moderation in the fuel layer, and epithermal absorptions as and fissions. The results obtained are very near those obtained for the idealized case in ORNL CF-58-1-4. (auth)
Date:
April 15, 1958
Creator:
Ergen, W.K.
Object Type:
Report
System:
The UNT Digital Library
HRP DYNAMIC CORROSION STUDIES (IN-PILE DEVELOPMENT). SUMMARY OF RUNS HT- 20, HT-21, AND HT-22 (THORIUM OXIDE SLURRY)
and HT-22 are described. These runs were made to determine the handling characteristics of a slurry containing thoria calcined at 1600 deg C and to evaluate the operation of the 5-gpm slurry pump. The experimental procedures are described. It was concluded that 1600 deg C calcined 0.7 mu mean particle size thoria can be satisfactorily circulated using the 5-gpm pump. (J.R.D.)
Date:
April 15, 1958
Creator:
Hubbard, D.W.
Object Type:
Report
System:
The UNT Digital Library
HRT DOME WALL TEMPERATURE
Maximum HRT dome wall temperatures for reactor powers up to 10 Mw were calculated for both an insulated amd uninsulated dome. Temperatures exceeding 315 deg C in the fuel solution flowing through the HRT dome section can cause phase separation which results in excessive corrosion rates. The results, based on very conservative assumptions, inticated wall temperatures exceeding 315 deg C could occur in the insulated dome when operating the reactor at 10 Mw. Using the same conservative assumptions, the analysis of the uninsulated dome indicated wall and bellows temperatures below 300 deg C. (auth)
Date:
April 15, 1958
Creator:
Claiborne, H.C.
Object Type:
Report
System:
The UNT Digital Library