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Evaluation of macroreticular anion exchange resin - RTA-893-R

Description: The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a c… more
Date: June 7, 1965
Creator: Baumann, E. W.
Partner: UNT Libraries Government Documents Department
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Underground radioactive materials in 100-H and F plants

Description: At 100-H Area there are 13 locations and at 100-F Area 16 locations where radioactive material was deposited underground. Five of these locations, 2 at 100-H and 3 at 100-F, have been permanently terminated as burial sites in compliance with Radiation Control Standards. They contain solid waste with significant quantities of long-life radionuclides. Burial locations within the 105 Building exclusion fences were not marked with permanent posts as the exclusion fences are sufficient marking for s… more
Date: October 29, 1965
Creator: Herman, G. Jr.
Partner: UNT Libraries Government Documents Department
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Problems associated with the extension of the stratigraphic units of south-central Washington. Part II. The post basalt sediments

Description: There are four district stratigraphic units within the Pasco Basin which if interpreted on the basis of recent field evidence and described properly could be traced over most of southeastern Washington. At the present time these post-basalt sediments are described in the literature in such a way as to make extensive correlations impossible. Some descriptions overlap more than one unit whereas others describe only a part of the unit. It is proposed that all interested geologists in the Pacific N… more
Date: March 26, 1965
Creator: Brown, D.J. & Brown, R.E.
Partner: UNT Libraries Government Documents Department
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KINETICS OF THE HYDROLYSIS AND ALCOHOLYSIS OF TETRAPOLYPHOSPHATEESTERS ('ETHYLMETAPHOSPHATE')

Description: 'Ethyl metaphosphate' or tetrapolyphosphate esters are a potentially useful starting material for the preparation of polynucleotides. The kinetics of the reactions of the esters with excess water and ethanol have been measured by means of p{sup 31} n.m.r. and IR spectroscopy. Upon the addition of specific amounts of water or ethanol, substances could be prepared which consist mainly of linear tetrapoly-, tripoly- or pyrophosphate esters containing smeller amounts of other polyphosphates and ort… more
Date: March 1, 1965
Creator: Burkhardt, Gottfried; Klein, Melvin P. & Calvin, Melvin.
Partner: UNT Libraries Government Documents Department
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OXYGEN 18 EXCHANGE REACTIONS OF ALDEHYDES AND KETONES

Description: Using infra-red spectroscopy, the equilibrium exchange times have been determined for a series of ketones, aromatic aldehydes, and {beta}-ketoesters reacting with oxygen 18 enriched water. These exchange times have been evaluated in terms of steric and electronic considerations, and applied to a discussion of the exchange times of chlorophylls a and b and chlorophyll derivatives.
Date: December 1, 1965
Creator: Byrn, Marianne & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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CHEMICAL EVOLUTION

Description: How did life come to be on the surface of the earth? Darwin himself recognized that his basic idea of evolution by variation and natural selection must be a continuous process extending backward in time through that period in which the first living things arose and into the period of 'Chemical Evolution' which preceded it. We are approaching the examination of these events by two routes. One is to seek for evidence in the ancient rocks of the earth which were laid down prior to that time in whi… more
Date: June 1, 1965
Creator: Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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QUARTERLY PROGRESS REPORT Research and development activities: fixation of radioactive residues. July-September 1965

Description: The calcined-waste containers produced during the Hot Cell Pilot Plant experiments in 1962 and 1963 have generated a maximum pressure of 3 psig. Design verification tests with the prototype spray calciner showed satisfactory performance when producing high melting point powders. Later tests on other feeds showed poor atomization and cake buildup in the calciner. Design of the prototype equipment is complete. Procurement and fabrication of prototype equipment is done except for a few cleanup ite… more
Date: October 1, 1965
Creator: Platt, A.M. (ed.)
Partner: UNT Libraries Government Documents Department
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Army gas-cooled reactor systems program. ML-1 pressure vessel technology evaluation. Summary report

Description: A limited program of evaluation of the ML-1 technology as related to the design of the calandria/pressure vessel assembly was completed. This work included: a photoelastic experimental program which resulted in the conclusion that values recommended by Langer and O'Donnell for the effective elastic constants employed in the analysis of ligament stresses in the ML-1 type tube sheets in the past results in a good approximation of the bending constants but in a value of the tensile elastic modulus… more
Date: July 1, 1965
Creator: Eggert, W. K. & English, W. F.
Partner: UNT Libraries Government Documents Department
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Use of total beta counts to estimate GI tract dose rates

Description: It was the practice for several years to estimate the potential dose rate to the gastrointestinal from sanitary water sources by evaluating the results of radiochemical analysis of individual nuclides. The proposed method estimates the GI tract dose from Pasco and Richland domestic water from measurements of the total beta activity, and permits more frequent and more economical evaluation of a variable source of radiation exposure. Beginning with 1964 data, the GI tract dose rate for Richland a… more
Date: October 25, 1965
Creator: Hall, R.B.
Partner: UNT Libraries Government Documents Department
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Computer calculation of angular momentum coupling coefficients and of (d,p) stripping reaction cross section. Technical report No. 14. [B53 DWC, B53GOR, B53RIM, B53SIX, in FORTRAN]

Description: A theoretical expression for the stripping differential cross section is derived and prepared for computer evaluation. Input information is provided for the code B53DWC, which calculates this cross section, and the codes B53GOR, B53SIX, and B53RIM, which evaluate 3-J, 6-J, and 9-J coefficients. (RWR)
Date: February 1, 1965
Creator: Strobel, G.L.
Partner: UNT Libraries Government Documents Department
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710 reactor program. Progress report No. 17

Description: This report is the seventeenth in a series of progress reports of the advanced high-temperature gas reactor - 710 program. This report describes the work performed and progress made from September 1 to October 31, 1965 on the following current tasks in the 710 program: Development of Refractory-Metal Fuel Elements; Critical Experiments of Fast-Spectrum, Refractory-Metal Reactors; Experimental Reactor Preliminary Design and Development; Test Facilities Design and Evaluation; and Investigations o… more
Date: December 1, 1965
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 43: SNAP fuel particle dispersion

Description: An evaluation of particle dispersion from natural and artificial sources has been made relating this information to circulation processes in the mesosphere, stratosphere, and troposphere. The data on natural particle and nuclear debris dispersion have been interpreted in terms of their significance in regard to SNAP fuel reentry dispersion and extended by various fall-out time and dispersion calculations.
Date: June 9, 1965
Creator: Johnson, H.E.
Partner: UNT Libraries Government Documents Department
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Experimental heat transfer distribution on the SNAP 10A reactor

Description: Heating distributions have been obtained for the SNAP 10A reactor by means of a thermal paint technique in the Rhodes and Bloxsom 60 in. hypersonic wind tunnel. Data and correlations are presented only for those reactor components where the ratio of the local heat transfer to that on the stagnation point of the calibration sphere was found to be independent of tunnel conditions. It is shown that these heating distributions can be applied directly to reentry conditions provided the thermally pai… more
Date: January 29, 1965
Creator: Hopenfeld, J. & Toews, R.E.
Partner: UNT Libraries Government Documents Department
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Thermo-physics technical note No. 56: a parameter study of properties and mechanisms affecting the reentry ablation of SNAP fuel particles

Description: The results are presented of a parameter survey of the properties and mechanisms affecting the reentry ablation of SNAP fuel particles. The following properties and mechanisms were studied: aerodynamic heating, oxidation, oxide vaporization, metal vaporization, particle emissivity, specific heat, density, velocity, and initial size. These studies were made for particle release altitudes ranging from 170,000 to 228,000 feet.
Date: December 7, 1965
Creator: Sayles, C.W.
Partner: UNT Libraries Government Documents Department
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Status of plant assistance irradiations as of July 16, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. … more
Date: August 3, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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Status report of confinement studies Douglas United Nuclear operated reactors

Description: Confinement studies on the Hanford Production reactors were started in March at the request of the Richland Operations Office. The confinement studies were then undertaken with the following objectives established: (1) review and reestablish if necessary, the maximum credible accident for the production reactors operated by Douglas United Nuclear (DUN); (2) evaluate the present confinement systems under the Code of Federal Regulation Title 10, Part 100, Reactor Site Criteria, for the maximum cr… more
Date: November 30, 1965
Creator: Spink, J. R. & Fifer, N. F.
Partner: UNT Libraries Government Documents Department
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Production Test IP-719: The effect of water plant variables on effluent activity. Final report

Description: One source of the parent materials which are converted into the radioisotopes in reactor effluent is the impurity content of Columbia River water. It has been demonstrated that as the efficiency of removal of the radioisotope parent materials increases, the amount of radioisotopes in the reactor effluent decreases. An example of this is the activity reduction which results from the use of high alum feed. In order to determine whether effluent activity would be influenced by the length of filter… more
Date: February 23, 1965
Creator: Geier, R. G.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, March 1965

Description: This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.
Date: April 22, 1965
Partner: UNT Libraries Government Documents Department
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Fission gas inventories and estimated releases from PRTR HPD fuel

Description: The PRTR is entering a phase of operation in which there is an increased danger of high level fission product release from failed fuel. The higher fuel operating temperatures result in a much larger percentage fission gas release from the fuel crystal; also it is believed that the central voids and inter-crystal cracks greatly improve the transport of fission gases from the far end of a fuel rod to a defect location. 6 tabs.
Date: September 21, 1965
Creator: Stoddard, J. A.
Partner: UNT Libraries Government Documents Department
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Exposure data, Y test hole - C reactor

Description: This report gives the exposure data for the C Reactor at the Hanford Reservation February 1965.
Date: February 25, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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