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Sheet Metal Can Furnace

Description: A need for a small vertical cylinder-type furnace arises frequently in the Chemistry Department at the Lawrence Radiation Laboratory (LRL). Adequate heat is the major requirement; close control or calibration is not usually necessary. A heating unit of this type can either be used for quickly concentrating solutions in centrifuge cones or, by the addition of a refractory pedestal--can be made into a crucible furnace for size 0 and 00 crucibles. Because much of the chemistry done at LRL is with radioisotopes, disposal of contaminated equipment is an important consideration. In general, furnaces are difficult to decontaminate, hence there was a need for a disposable type. Because nothing meeting the requirements seemed to be commercially available, the Health Chemistry Department made up a simple furnace that has proved useful.
Date: August 17, 1961
Creator: Doyle, Richard C. & Phillips, Will D.
Partner: UNT Libraries Government Documents Department
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Fabricating Liquid-Hydrogen Targets From Mylar

Description: The increasing popularity of liquid-hydrogen targets in physics research has emphasized the need for containers with maximum beam transparency (i.e., thin walls and low Z) and suitable strength at cryogenic temperatures. Fabrication of a Mylar container satisfying these requirements is described here.
Date: August 17, 1961
Creator: Mehr, David L.
Partner: UNT Libraries Government Documents Department
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Calibration Of Bridgman Anvils, A Pressure Scale To 125 Kbars

Description: It is shown that a radial pressure gradient exists in the silver chloride when it is used as the pressure transmitting medium in Bridgman anvils. The gradient can be obviated by the use of circular sections of wire. The center of curvature of the wire hoop is made coincident with the anvil center. When the inner and outer diameters of the pyrophyllite retaining ring are 1/2 and 7/16" respectively, the pressure, P, is P = (0.725 + 0.468R) L where R is the fractional displacement from the center, and L is the average pressure as determined from the total load and area of the anvil face. The above appears to be valid to 125 Kbars. The Bismuth 6-8 transition is found to accur at 88+3 Kbars.
Date: August 1961
Creator: Montgomery, Peter W.; Stromberg, Harold; Lura, George H. & Jura, George
Partner: UNT Libraries Government Documents Department
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The Crystal Structure Of Cobalt Sulfate Hexahydrate

Description: Calorimetric measurements by Rao and Giauque (1960) showed some unaccountable residual entropy in crystals of [formula] at low temperatures. We have investigated the crystal structure in search of an explanation of the disorder. The resulting structure offers no possibility of disordered rings of hydrogen bonds such as were found in [formula], nor do we find any other explanation of the entropy discrepancy.
Date: August 1961
Creator: Zalkin, Allan; Ruben, Helena & Templeton, David H.
Partner: UNT Libraries Government Documents Department
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The Sideband Technique In A Variable Frequency NMR Spectrometer

Description: The purpose of this Note is to point out the advantages of the sideband technique over the derivative method in wideline NMR spectroscopy. In the sideband technique the absorption spectrum is recorded directly and the modulation amplitude is no longer a determining factor in the resolution.
Date: August 1961
Creator: Acrivos, J. V., 1928-
Partner: UNT Libraries Government Documents Department
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A Pulsed Nanosecond Light Source

Description: A system for scintillations from nuclear events has been developed and is presently in use at the Lawrence Radiation Laboratory. This paper primarily describes the pulsed light source used to simulate nuclear events; it also describes the necessary nanosecond pulse techniques to measure the light source parameters and to operate large numbers of lamps. Considerations concerning distribution networks are shown. Use of the light source as a spark gap trigger is also discussed.
Date: August 4, 1961
Creator: Innes, Thomas G. & Kerns, Quentin A.
Partner: UNT Libraries Government Documents Department
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Remote Plastic Bag Passout Unit For High-Level Radiochemical Operations

Description: This system presents a method for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. In addition, the polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak-rate seal. Our system employs an interchange box (the Passout Box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator teamed with the above units handles all operations.
Date: August 1961
Creator: Fleischer, E. S. & Parsons, T. C.
Partner: UNT Libraries Government Documents Department
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Close-Capture Adsorption System For Remote Radioisotope Chemistry

Description: Molecular sieves are synthetic zeolites which, when dehydrated, contain a network of empty pores and cavities that constitute almost 50% of the total volume of the crystals. They have the unique property of adsorbing within these cavities only those molecules that are small enough to pass through the pores of the crystals, Molecular sieves have a very strong affinity for water and other polar molecules. It is this selective property plus their stability and reasonable cost that make them of interest for the application described herein.
Date: August 17, 1961
Creator: Spencer, Neil C.; Parsons, Thomas C. & Howe, Patrick W.
Partner: UNT Libraries Government Documents Department
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Double Meson Production In Proton-Deuteron Collisions. II

Description: In a previous publication we reported measurements of the momentum spectra of He<sup>3 and H<sup>3 nuclei produced in collisions of 740-MeV protons with deuterium. The He<sup>3 spectrum exhibited an anomaly in the form of a peak in the region corresponding to double pion production. For reactions resulting in a He<sup>3 the two pions (or particle) can be isotopic spin states 0 or 1; if a H<sup>3 nucleus results only 1 = 1 is allowed. We have since repeated the experiment with a new arrangement which enabled us to measure both the He<sup.3 and H<sup>3 spectra with improved resolution and accuracy.
Date: August 1961
Creator: Booth, Norman E.; Abnashian, Alexander & Crowe, Kenneth M.
Partner: UNT Libraries Government Documents Department
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A Manual of Experiments in Reactor Physics

Description: Nuclear processes are random in character, and, accordingly, are amenable to statistical treatment. In 1905, shortly after the discover of natural radioactivity, E. Von Schweldler showed that the analytical description of the decay distribution of radioactive substances followed from probability considerations regardless of the mechanism involved in the process of atomic disintegration.
Date: August 1961
Creator: Valente, Frank Anthony; Davidson, J. P. (John Pirnie), 1924-; Gisser, David G.; de Moraes, Octavio L.; Bryce, Donald H. & LoGuidice, Joseph M.
Partner: UNT Libraries Government Documents Department
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Engineering Testing of the F-48 Columbium Alloy

Description: The F-48 columbium base alloy maintains useful mechanical properties for structural application up to 2600 degree F. Short-time tensile and creep rupture strengths have been determined for four F-48 plates, each from a different heat and with a different work history. Flow testing in a high-temperature, high-pressure air stream has been conducted to study oxidation behavior of the bare meatal. Auto-ignition is found to occur at a stream temperature of 2600 degree F. The phenomenon appears to be temperature dependent only. Development of an oxidation protection coating, utilizing environmental flow test apparatus, is proceeding.
Date: August 2, 1961
Creator: Cox, John W. & Werner, Richard W.
Partner: UNT Libraries Government Documents Department
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Identification of Curium-242 in Irradiated Neptunium

Description: Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."
Date: August 1961
Creator: Carothers, Glenn A.
Partner: UNT Libraries Government Documents Department
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Surge suppressors for the PRTR process tube flow meters

Description: Each tube of the PRTR is provided with flow monitoring equipment consisting of a venturi flow meter in the inlet piping, sensing lines containing valves, and a Panellit flow transmitter. The flow transmitter does three things: converts the pressure drop signal of the venturi to a visual readout; provides an electrical signal for recording; and provides a signal to the safety circuit which causes a reactor scram should the flow increase or decrease beyond pre-set valves. After startup of the PRTR, it was found that the readings of flow meters on those process tubes which connect near the inlet of the bottom ring headers were fluctuating excessively. As an interim measure during the power tests at low reactor powers, the meter fluctuations were reduced by throttling the valves in the sensing lines from the flow venturi to the flow meter. This was recognized as being questionable for a permanent solution since this practice introduces an unknown and variable lengthening of the response characteristics of the meter. An experimental program was therefore undertaken to determine the degree of valve throttling which might be appropriate for fluctuation suppression and to device other and better methods of suppression. The experiments show that throttling of valves in the flow transmitter sensing lines is not a satisfactory way of decreasing the fluctuations. The valves must be closed to about 1/4 open before they decrease fluctuations significantly. Further closure to about 1/8 open causes an excessive lengthening of the response characteristics of the transmitter. This provides only a very narrow range of valve positions which are permissible and effective. The increased hydraulic flow resistance of 3--5 foot lengths of 1/16-inch tubing in the sensing line causes the flow transmitter system to become nearly critically damped. This will eliminate the oscillatory behavior of the readings without causing …
Date: August 11, 1961
Creator: Hesson, G. M.; Thorne, W. L. & Batch, J. M.
Partner: UNT Libraries Government Documents Department
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Serious Radiation Event - Hanford Capabilities

Description: The need for an industrial plant to know its capabilities to rescue personnel and minimize damage to vital operating equipment in the event of a serious accident has long been recognized. Although Hanford`s experience has been without a serious radiation event as characterized in this report, it is prudent to have an objective assessment of the capabilities which do exist and an analysis of the general capabilities which the plant should possess to maximize the effectiveness of rescue action in such an event and to limit the consequences to personnel, vital equipment, and the surrounding environs. It in the purpose of this report to: (1) make an assessment of the capabilities which are currently in place at Hanford to handle the multitude of serious problems arising from a serious radiation event; and (2) define the level of capability which the Hanford Atomic Products Operation should possess to minimize the consequences of such an accident. It is not the intent of this presentation to discuss the possibilities, probabilities, prevention or courses of serious radiation events.
Date: August 15, 1961
Creator: Keene, A. R.; Unruh, C. M.; Backman, G. E. & Carter, L. A.
Partner: UNT Libraries Government Documents Department
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Supplement A to design of PT-IP-263-A-FP, evaluation of chemically nickel plated fuel elements

Description: Irradiation of the initial test in this program involving ten tubes of alternately charged nickel-plated C-64 alloy clad test elements and X-80001 alloy control elements has been successfully completed. The test indicated that the nickel-plate spalling problem has been resolved, as no significant spalling or flaking was observed during the post-irradiation examination. The second test in this program will be to verify that the nickel-plate integrity problem has been solved by irradiating a pilot loading (up to 100 charges) of fuel elements which have been nickel-plated on a production basis.
Date: August 22, 1961
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Hazards review Phase 1 fission product processing in B-plant

Description: Future operation of B-Plant for Phase I fission product processing involves may of the hazards associated with current chemical Processing Department activities in both the Purex and Redox Plants. The specific B-Plant hazards under Phase I operations are discussed in this report from the standpoint of comparable Purex and Redox hazards.
Date: August 24, 1961
Creator: Michels, L. R. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
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Report to the working committee

Description: Topics include: uranium quality and technology, fuel assembly technology, irradiation experience, E-N program, projection fuel program, overbore fuel program, Ni-plated Al-clad fuel elements, fuel element development, NPR program.
Date: August 29, 1961
Creator: Stringer, J. T. & Minor, J. E.
Partner: UNT Libraries Government Documents Department
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Production test IP-431-A expansion of overbore test facilities C Reactor

Description: The objective of this production test is to authorize the installation of at least 40 additional large size Zircaloy process tubes in graphite channels that have been enlarged to 2.275 inches at C Reactor and to charge these tubes with large diameter (CVIN) fuel elements to obtain preliminary conversion ratio data and further qualitative data regarding the irradiation behavior of large diameter fuel element designs.
Date: August 11, 1961
Creator: Van Wormer, F. W.
Partner: UNT Libraries Government Documents Department
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Measurement procedures for purified birch

Description: Since start-up of the neptunium recovery and purification program at HAPO, the neptunium-has been subjected to the following process steps: Production of crude neptunium nitrate by the Redox and Purex plants; Production of purified neptunium nitrate, using an anion exchange process, in research and development facilities operated by CPD`s Process Chemistry Operation; Production of neptunium oxide (NpO{sub 2}) by Process Chemistry. Mixing the NpO{sub 2} powder with aluminum powder and incorporation in an aluminum-clad-target element, done by the Plutonium Metallurgy Operation of Hanford Laboratories; and Irradiation of the target elements in the Savannah River reactors; and Chemical reprocessing of the irradiated target elements at Savannah River to recover the desired plutonium-238 and the unconverted neptunium. As frequently happens to between-contractor transfers, neptunium material balances between Hanford`s NpO{sub 2} and Savannah River`s recovered neptunium have sometimes been poorer than expected. Because of wide spread interest in this problem, it was deemed desirable to put on record a description of the measurement techniques which have been used at Hanford for NpO{sub 2} and the improvements which have been made in the analytical methods. The measurement methods used for purified nitrate are also described.
Date: August 14, 1961
Creator: Buckingham, J. S.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of transverse cracked rupture from 2986 DR (Rm 427)

Description: An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoint where the transverse cracks occurred and was least in the male end. Metallography of both longitudinal and transverse sections revealed that the metal quality of the fuel vas good. Cracks which originated from the oxide extended in both the longitudinal and transverse directions. The fuel near the core, which was insulated by oxide, was annealed but had not been heated into the uranium beta phase. One transverse crack which appeared to have water entry was observed approximately two inches from the male end. The ingot number was UZ 5751 B. After removal of the cladding at the ends, the uranium was bright dip etched and no defects were observed in the surface metal.
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of Zircaloy-2 clad heavy-walled tubular fuel element in KER Loop-3

Description: On the 0000 -- 0800 shift, December 9, 1960, the delayed neutron monitor on KER Loop 3 gave a high coolant activity signal indicating a possible fuel element failure in this loop. KE Reactor was shut down immediately thereafter. This report is being written to summarize the events pertinent to this KE Reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken from the KER Loop 3 system.
Date: August 21, 1961
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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