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Chemical Processing Department monthly report, November 1959

Description: The November 1959 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)
Date: December 21, 1959
open access

DISCUSSION OF PERFORMANCE CALCULATIONS OF NUCLEAR ROCKET ENGINES

Description: BS>Some of the fundamental relationships in a nuclear rocket engine are discussed. The equations required to calculate the performance of the rocket are presented. The problems associated with these calculations are also pointed out. (auth)
Date: December 21, 1959
Creator: Semple, E.L.
open access

Final report on the fuel and target element evaluation at increased irradiation levels for tritium production: Production tests 313-105-35-M and 105-562-A

Description: The C Reactor was proposed for producing tritium. To evaluate the performance of enriched U-Al J elements and natural Li-Al alloy target (N) elements, 60 charges containing both J and N pieces were irradiated under a variety of conditions in C Reactor. No ruptures were sustained; however Tube 3276-C was discharged because of a suspect. Corrosion rates of J elements were not worse than for natural U irradiated under same conditions. Differences between corrosion of J elements prepared by three d… more
Date: December 21, 1959
Creator: Hodgson, W. H.
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Isotope-producing control rods

Description: In accordance with the NPR technical criteria which require that provisions be made for useful isotope production in the control rods, both isotope-producing and non-production rods have been designed. Design Analysis has been requested by Reactor Plant Design to specify the number and location of the isotope rods for the initial installation. This choice, however, cannot be made without knowledge of the fuel element characteristics and a prediction of the reactor operating techniques. Some of … more
Date: December 21, 1959
Creator: Simpson, D. E.
open access

Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

Description: Property changes to common graphites resulting from reactor irradiation depends strongly on the temperature of exposure. Radiation affects at 30 C and 400 to 500 C are quite well known; however, at intermediate temperatures, results are not well known although a large volume of graphite in most reactors operate in this range. Production test, IP-22A, was reactivated, after a dormant period of many months, to study radiation damage between 30 and 400 C. This report concerns mainly the experiment… more
Date: October 21, 1959
Creator: Koyame, K.
open access

Design of Chemical Processing Plant for Homogeneous Reactor Test

Description: This report describes the design of the plant that was construrcted to remove insoluble fission and corrosion products from the circulating fuel solution of the Homogeneous Reactor Test (HRT). (auth)
Date: October 21, 1959
Creator: Rom, A. M. & Weeren, H. O.
open access

EXPERIMENTAL AND ANALYTICAL STUDIES OF REFLECTRO CONTROL FOR THE ADVANCED ENGINEERING TEST REACTOR. PART A. EXPERIMENTAL STUDIES WITH THE REFLECTOR CONTROL SYSTEM MODEL. PART B. ANALYTICAL STUDIES OF REFLECTOR CONTROL

Description: Studies of reflector control for the Advanced Engineering Test Reactor were made. The performance of various parts of the reflector control system model such as the safety reflector and the water jet educator, boric acid injection, and demineralizer systems is discussed. The experimental methods and results obtained are discussed. Four reflector control schemes were studied. The schemes were a single-region and three-region reflector schemes two separate reflectors, and two connected reflectors… more
Date: October 21, 1959
Creator: Bertelson, P.C. & Francis, T.L.
open access

Neutron prompt burst assembly proposal

Description: The development of new techniques of initiating nuclear weapons has amplified the requirement for an accurate knowledge of the probability of initiation as a function of the various parameters involved. The results of the codes presently used to calculate these probabilities are self-consistent, but have been shown to be quite sensitive to the value of fission cross section used. Accordingly the critical assemblies group vas requested informally by small weapons division to investigate the feas… more
Date: October 21, 1959
Creator: Christie, E. R.
open access

Transient Pressures Developed by Sodium-Nitric Acid Reactions

Description: The Atomic Energy Commission has assigned Hanford Atomic Products Operation the responsibility of reprocessing some of the slightly enriched uranium fuel elements from nuclear power reactors. Some stainless steel clad fuel elements contain sodium or a sodium-potassium alloy as a heat transfer medium between metallic core and outer sheath. The nature of the reaction between water and sodium is well known; however, the reaction between sodium and an oxidizing acid is more energetic and not so wel… more
Date: October 21, 1959
Creator: Huck, C. E. & Shefcik, J. J.
open access

Chemical Processing Department Monthly Report: August 1959

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: September 21, 1959
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
open access

DOSE AND FLUX MEASUREMENTS ON GODIVA RADIATION EFFECTS EXPERIMENTS

Description: Flux and dose measurements of fast neutrons, thermal neutrons and gamma rays under perturbing conditions using Godiva as a source are described and discussed. The limitations of single monitoring devices are noted. It is pointed out that in order to improve the accuracy of flux and dose measurements in radiation effects studies, specific detectors must be used at the position of the experimental object. (auth)
Date: September 21, 1959
Creator: Harris, P.S.; Montoya, E.F. & Schweitzer, W.H.
open access

Irradiation Processing Department monthly record report, August 1959

Description: This document details activities of the irradiation processing department during the month of August 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operation; and financial operation.
Date: September 21, 1959
open access

Pressure and Thermal Stresses at a Pipe Attachment to a Sphere

Description: Abstract: Design nomographs and equations have been prepared for determining the bending stresses and hoop stresses at the junction of a cylinder and sphere when: (1) Internal pressure exists in the sphere and (2) There is a difference in average temperature between the cylinder and the sphere. A correlation of calculated stresses and photoelastically determined stresses for models with internal pressure is presented.
Date: September 21, 1959
Creator: Deagle, Lorenzo
open access

Production test IP-285-C measurement of operating temperatures of uncooled thermal shield cooling tube

Description: The purpose of this test is to obtain data that may be used as a basis for revising certain Process Standards applying to the cooling or existing reactor shields. The data may also be useful in connection with NPR thermal shield design work. The fact that one of the H reactor bottom thermal shield cooling tubes presently has a flow blockage makes possible an immediate opportunity for test data without undue risk other than that already encountered. Procedures, costs, and hazards of the test are… more
Date: September 21, 1959
Creator: Smalley, W. L.
open access

Air-Core Strong Focusing Synchrotron

Description: The following report is based on work performed under the auspices of the U.S. Atomic Energy Commission. The purpose of this report is to describe an air-core strong focusing synchrotron and its functions.
Date: August 21, 1959
Creator: Christofilos, Nicholas C.
open access

Chemical Processing Department monthly report, July 1959

Description: Pu production from separation plants was only 65% of the monthly commitment owing to Purex difficulties. UO{sub 3} production and shipments both met schedules. Although unfabricated Pu metal production was reduced, all shipping commitments were met on schedule. Purex equipment responded satisfactorily to decontamination. 860,000 Ci of Ce{sup 144} were recovered from Purex Conc. IWW. The all-Ti L-3 concentrator loop was installed in the Redox Pu Concentrator. The safety of the slag and crucible … more
Date: August 21, 1959
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Design of Production Test IP-247-A-8-FP, irradiation of 1.47% enriched self-supported I&E fuel element in ribless process tubes. Revision

Description: To evaluate the self-supported fuel element concept, tests are underway to determine the performance of collapsible bridge-rail supported fuel elements in ribless process tubes under present reactor conditions at B Reactor. It appears expedient, however, to extend this evaluation to future operating conditions in order to establish the relative feasibility of conversion to self-supported fuel elements in ribless tubes in present reactors. Utilization of 1.47% U-235 enrichment will provide fuel … more
Date: August 21, 1959
Creator: Hodgson, W. H. & Hall, R. E.
open access

Irradiation Processing Department monthly record report, July 1959

Description: This document details activities of the irradiation processing department during the month of July 1959. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; facilities engineering operation; employee relations operation; and financial operation.
Date: August 21, 1959
open access

PROGRESS ON THE DEVELOPMENT OF URANIUM CARBIDE-TYPE FUELS

Description: It has been corfirmed that uranium monocarbide can be prepared by reacting uranium metal powder with methane at about 650 C, and that sintered carbides of greater than 90% of theoretical density can be made. The cast density of carbides has been found to vary from 13.56 g/cm/sup 3/ for UC to 11.7 g/cm/sup 3/ for UC/sub 2/. The electrical resistivity of cast carbides has been found to vary from about 40 microhm-cm for UC to about 90 microhm-cm for UC/sub 2/ . About 500 ppm of iron or silicon has… more
Date: August 21, 1959
Creator: Rough, F.A. & Chubb, W. eds.
open access

WELDED SEAL-RING VACUUM CLOSURES

Description: The development of bakeable high-vacuum flanges for the ORNL PIG Facility is reported. The general design approach for this type flange is to obtain a bakeable vacuum seal by first welding thin metal rings to a set of heavy metal flanges, and then edge-welding the rings together. This design sllows the option of O-ring sealing for nonbaked operation. A number of flange designs are discussed together with fabrication inspection, testing, and installation and maintenance information. (auth)
Date: August 21, 1959
Creator: Michelson, C.
open access

An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
open access

Chemical Technology Division, Unit Operations Section Monthly Progress Report for April 1959

Description: A concentration cell electrode was installed in a fritted glass surface and was used to measure the surface KCl concentration while water was being transpired through the surface into a mixed tank of 0.1 M KCl. The results from the first Fluorox run made with crude UF/sub 4/ showed that 85.3% of the theoretical amount of UF/sub 6/ was accounted for, with 17.9% being collected in cold traps and the remainder being consumed in various side reactions. Installation was completed of apparatus to stu… more
Date: July 21, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
open access

INVESTIGATION OF MECHANICAL METHODS OF SCALE REMOVAL FROM HRT HEAT EXCHANGERS

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4 in OD X 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employed i… more
Date: July 21, 1959
Creator: Gabbard, C.H.; Eissenberg, D.M.; Moyers, J.C. & Namba, I.K.
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