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The [Sigma/Alpha] Branching Ratio Of [Y*1]

Description: Recently a T=1 resonance in the [Alpha w] system called [Y*1] has been observed with a mass of 1385 Mev. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the Alpha w and Sigma w systems predicted by global symmetry corresponding to the (3/2, 3/2) resonance of the wN system, (2) a spin-1/2 Y-w resonance resulting from a bound state in the KN system. The position and width of the observed [Y*1] resona… more
Date: April 25, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W., 1911-1988; Eberhard, Phillippe; Good, Myron L.; Graziano, William; Ticho, Harold K., 1921-2020 et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE Epsilon*/Lambda BRANCHING RATIO OF Y*1

Description: Recently a T = 1 resonance in the {Lambda}{pi} system called Y*{sub 1} has been observed with a mass of 1385 Mev. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}{pi} and {Sigma}{pi} systems predicted by global symmetry corresponding to the (3/2, 3/2) resonance of the {pi}N system; (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the KN system. The position and width of t… more
Date: April 25, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W.; Eberhard, Philippe; Good,Myron L.; Graziano, William; Ticho, Harold K. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP

Description: Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date: July 25, 1961
Creator: Atz, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING

Description: The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)
Date: September 25, 1961
Creator: Bresee, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Swaging Over Unground Pellets

Description: This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date: January 25, 1961
Creator: Brown, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interim report: Some temperature and swelling data on Zircaloy-2 clad coextruded fuel elements

Description: This report provides some temperature and swelling data on Zircaloy-2 clad, coextruded fuel elements irradiated in the KER loops and in the GEH-3 {times} 3P7 loop at the ETR. Data on both rod cluster fuel elements and tubular fuel elements are included. Density changes, where density measurements were made, have also been included. These data are preliminary and are subject to change.
Date: January 25, 1961
Creator: Call, R. L. & Geering, G. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proposal for charging the sixth rupture fuel element experiment: GEH-10, 46, 47

Description: The objective of the test discussed in this report is to verify further the corrosion rate of irradiated tubular fuel elements under conditions of high specific power and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. A proposal to charge two tubular fuel elements into the GEH-P7 Loop has been made. The upper fuel element of the two has been irradiated to 1660 MWD/T in a Hanford reactor. A hydraulic cylinder will be attached to the upper fuel el… more
Date: January 25, 1961
Creator: Call, R. L. & Kaulitz, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Nuclear Calculations for the SM-2 Core 1

Description: The results of a limited analysis of the extended SM-2 critical experiments are given. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SMi-2 Core I. A new reference B-l0 loading was derived based on analysis and experimental measurements. Calculations of power distributions and burnup behavior of the reference core are presented and comparisons to available measured data made. (auth)
Date: September 25, 1961
Creator: Fried, B. E.; Beam, R. H. & Bobe, P. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spectrographic Determination of Impurities in Hafnium

Description: A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)
Date: August 25, 1961
Creator: Ginther, B. E. & Wheeler, G. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Barytes Concrete for Radiation Shielding: Mix Criteria and Attenuation Characteristics

Description: Concrete mix design criteria, based on existing theories of proportioning and specifically oriented toward the solution of radiation shielding problems, were developed. Effects of aggregate gradation, cement-to- aggregate ratio, and water content were examined. A barytes concrete, designed according to these criteria, was thoroughly investigated in the Lid Tank Shielding Facility. Relative effectivenesses of dry aggregates, aggregates plus cement, and cured concrete were compared through therma… more
Date: July 25, 1961
Creator: Grantham, W.J. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOW LEVEL WASTE TREATMENT BY ION-EXCHANGE, II. USE OF A WEAK ACID, CARBOXYLIC-&HENOLIC ION-EXCHANGE RESIN

Description: Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenoliccarboxylic resin, showed essentially the same results as those previously reported using a phenolic- sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has … more
Date: September 25, 1961
Creator: Holcomb, R.R. & Roberts, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Low level waste treatment by ion-exchange. II. Use of a weak acid, carboxylic-phenolic ion-exchange resin

Description: Laboratory results are presented for a flowsheet study of a process for decontaminating ORNL low level waste water. The water is adjusted to approximately pH 12 with NaOH, clarified, and passed through a bed of phenolic cation exchange resin. This study, using a phenolic-carboxylic resin, showed essentially the same results as those previously reported using a phenolic-sulfonic resin, i.e., radioactivities in ORNL waste were reduced to the order of 10% of MPC. The phenolic-carboxylic resin has … more
Date: September 25, 1961
Creator: Holcomb, R.R. & Roberts, J.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Supplement G, production test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: Irradiation of a third thermocouple train with a thermocouple element of the same design as used on the previous two trains, but with different train design and heater elements, is authorized to an exposure no greater than 1000 MWD/T. A third decontamination of KER-1 is also authorized.
Date: April 25, 1961
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Revision to optimization constants

Description: Tables are given for revised constants in the optimization model for charge-discharge rates, tube replacement rate, non-power-exposure- associated loss (EMISC), hours lost per rupture, and ruptured slug removal time in the reactors B, C, D, DR, F, H, KE, and KW.
Date: April 25, 1961
Creator: Newell, L. J. & Spencer, H. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Physical Metallurgy of Uncommon Metals

Description: Incremental couples at 10% intervals across the U-Nb binary system were prepared and diffused. Irradiation damage of nickel single crystals bombarded with 3-Mev electrons from a Van de Graaff generator were studied by Kossel line techniques. It was concluded that most defects anneal out below room temperature and all anneal out below 400 deg C. The cold-rolled texture of tantaium is described by (200) and (110) pole figures. This texture may be approximated by the ideal orientations, {112} <011… more
Date: April 25, 1961
Creator: Ogilvie, R. E. & Norton, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Model for Fission-Gas Release From Porous Fuels in Low-Permeability Containers

Description: A simple mathematical model was developed to describe the steady-state release rate of gaseous fission products from porous ceramic fuels in low- permeability containers. The resulting equations are used to analyze experimental release rate results obtained from a UC/sub 2/-fueled graphite fuel body enclosed in a low-permeability impregnated graphite container. The relative release rates of the fission-product species Kr/sup 85m/, Kr/sup 88/, and Xe/sup 133/ were predicted with reasonable succe… more
Date: August 25, 1961
Creator: Prados, John W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Flood Safety of the Mixed Spectrum Superheater

Description: Calculations are presented which show that the reactivity effect of flooding and unflooding the fast superheating section of the Mixed Spectrum Superheater can be made small by the addition of epithermal poisons to the superheater. The reactivity effects of flooding superheater sections ranging in size from 1.25 to 3.5 ft cubes and containing U/sup 23/5/sup >/oxide or Pu/sup 239/ oxide fuel and various amounts o f the epithermal poison europium were calculated. Reactivity changes during several… more
Date: May 25, 1961
Creator: Reynolds, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simulation of the Zirflex Process With an Analog Computer

Description: The Zirflex process was studied extensively at Hanford in the development of technology for the interim reprocessing of power reactor fuels. The process involves the dissolution of Zircaloy in aqueous ammonium fluoride - ammonium nitrate solution. It is of particular interest at Hanford because of the impending fuel recovery from Zircaloy-clad PRTR and NPR elements. The chemical kinetics of the Zirflex reaction were not fuily defined at the end of the original studies. However, a pseudo first o… more
Date: October 25, 1961
Creator: Smith, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FINAL STATUS OF GENERAL ENGINEERING LABORATORY AIR FLOW AND DUST TEST PROGRAM. PART I. PART II

Description: A full scale 15 deg sector of the P122 reactor configuration was constructed. The model was complete with respect to all internal cooling air passages, and reflectors, thermal shielding, and island reflector. The contract was terminated before any test data could be obtained. Investigation of the effect of atmospheric dust on performance of reactor systems using wire screen matrix fuel elements is reported. The interim conclusion is that dust would not limit aircraft performance or life. Work p… more
Date: May 25, 1961
Creator: Venneman, Walter F.; Lawrence, R. L. & Ryan, P. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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