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PION SCATTERING FROM A POLARIZED TARGET (open access)

PION SCATTERING FROM A POLARIZED TARGET

This report describes the use of a target containing polarized protons in a particle-scattering experiment. Positive pions of 246-MeV kinetic energy were scattered from the polarized protons. The parameter P that was measured is equivalent to that determined by analyzing the recoil-proton polarization in scattering from an unpolarized target. It has been measured to a higher accuracy than heretofore achieved in pion-proton scattering, at an energy and at angles inconvenient for double-scattering techniques.
Date: August 7, 1963
Creator: Chamberlain, Owen; Jeffries, Carson D.; Schultz, Claude H.; Shapiro, Gilbert & Van Rossum, Ludwig.
System: The UNT Digital Library
N-Reactor Department monthly report, October 1963 (open access)

N-Reactor Department monthly report, October 1963

This document details activities of the N-Reactor Department during the month of October 1963.
Date: November 7, 1963
Creator: unknown
System: The UNT Digital Library
N-Reactor Department monthly report, September 1963 (open access)

N-Reactor Department monthly report, September 1963

This document details activities of the N-Reactor Department during the month of September 1963.
Date: October 7, 1963
Creator: unknown
System: The UNT Digital Library
AlSi slopovers: studies, method of elimination and results (open access)

AlSi slopovers: studies, method of elimination and results

During fuel element assembly, a dip-brazing process., the aluminum can which is ultimately a jacket for a uranium core is protected from the molten AlSi solution by a steel sleeve. Once the can is inserted into the sleeve and thermal expansion is complete, upset metal rings prevent molten AlSi from flowing between the can and sleeve, a situation that warrants rejection. Passage of molten solution beyond upset metal to a point on the can wall not removed during the subsequent facing operation is called an ``AlSi Slopover`` or ``Slop.`` With discovery of a solution which would mask 8001-F aluminum alloy from molten AlSi, efforts were directed towards using this solution to eliminate AlSi stopovers. With proper application and control, PWR 125 proved that cans coated with PX1288 did not alloy AlSi in the molten state to pass beyond the upset metal region during canning. Since this material has been used on total production, the CPR rate has been greatly reduced. Percentage of rejects attributable to the CPR category is 0.5%.
Date: December 7, 1963
Creator: Schaffer, J. D.
System: The UNT Digital Library
N-Reactor Department monthly report, May 1963 (open access)

N-Reactor Department monthly report, May 1963

This document details activities of the N-Reactor Department during the month of May 1963.
Date: June 7, 1963
Creator: unknown
System: The UNT Digital Library
Report to the working committee from the General Electric Company, HAPO (open access)

Report to the working committee from the General Electric Company, HAPO

Information is presented on current reactor fuel development (uranium core production data, fuel performance, AlSi process development, and alternate process development) and NPR fuel development (fuel production status, KER loop testing, and process development).
Date: January 7, 1963
Creator: Stringer, J. T. & Minor, J. E.
System: The UNT Digital Library
Exceeding always-safe ratio in F-2 and F-1 tanks: Number 2, CY-63 (open access)

Exceeding always-safe ratio in F-2 and F-1 tanks: Number 2, CY-63

The always critically-safe ratio of plutonium to enriched uranium was exceeded in the F-2 and V-1 vessels on June 6, 1963. The allowable always-safe ratio at the time of the incident vas 627 grams per ton. The actual ratio achieved vas 673 grams per ton. This report details the investigation into events leading to the over-batch.
Date: October 7, 1963
Creator: Malody, C. W.
System: The UNT Digital Library
Interim report III, production test IP-560-A: Half-plant low dichromate, low pH water treatment at C Reactor (open access)

Interim report III, production test IP-560-A: Half-plant low dichromate, low pH water treatment at C Reactor

A half-plant low dichromate-low pH test was started at C Reactor on March 1, 1963. The test will demonstrate whether l.0 ppm sodium dichromate provides adequate corrosion inhibition when,the reactor coolant pH is 6.6. The test monitoring will consist of ex-reactor tube examinations, in-reactor.wall thickness measurements, coupons, visual examination of fuel elements and fuel element weight loss measurements. Previous interim reports have discussed the results obtained from the visual examination of two twenty column discharges obtained as follows: one discharge prior to the start of the test; one discharge such that the fuel was exposed to-coolant treated at both 7.0 and 6.6 pH. This report discusses the-results from.the visual examination and-weight loss measurements on fuel irradiated under test conditions, the results-from coupons-exposed in the downstream spacer pattern, and the ex-reactor examination,of two process tubes.
Date: November 7, 1963
Creator: Geier, R. G.
System: The UNT Digital Library
Preliminary report on CX-2 N-inner fuel tube number 1055-8 (open access)

Preliminary report on CX-2 N-inner fuel tube number 1055-8

The real cost of metallurgical examination of irradiated fuel elements is several times that of fuels before irradiation. Since post-irradiation study is necessary to determine the performance of prototype fuel designs in a reactor environment, complete physical characterization before irradiation provides an economical and efficient basis for comparing experimental data. Without such comparative study, unexpected damage to fuels in the reactor would be difficult, if not impossible, to interpret. This report presents such a characterization of one fuel element from a group of fuels prototypic of the initial charge in Hanford`s N-Reactor. This fuel element, 1055-8, is significant because it belongs to the Production Work Request CX-2 family of elements.
Date: February 7, 1963
Creator: Kuhlken, L. E. & Wheeler, R. G.
System: The UNT Digital Library
N-Reactor Department monthly report, December 1962 (open access)

N-Reactor Department monthly report, December 1962

This report details activities of the N-Reactor Department during the month of December 1962.
Date: January 7, 1963
Creator: Dickeman, R. L.
System: The UNT Digital Library
N-Reactor Department monthly report, July 1963 (open access)

N-Reactor Department monthly report, July 1963

This report details activities of the N-Reactor Department during the month of July 1963.
Date: August 7, 1963
Creator: unknown
System: The UNT Digital Library
N-Reactor Department monthly report, January 1963 (open access)

N-Reactor Department monthly report, January 1963

This report details activities of the N-Reactor Department during the month of January 1963.
Date: February 7, 1963
Creator: unknown
System: The UNT Digital Library
N-Reactor Department monthly report, April 1963 (open access)

N-Reactor Department monthly report, April 1963

This document details activities of the N-Reactor Department during the month of April 1963.
Date: May 7, 1963
Creator: unknown
System: The UNT Digital Library
N-Reactor Department monthly report, February 1963 (open access)

N-Reactor Department monthly report, February 1963

This report details activities of the N-Reactor Department during the month of February 1963.
Date: March 7, 1963
Creator: unknown
System: The UNT Digital Library
Aqueous Processing of Thorium Fuels, Part 2 (open access)

Aqueous Processing of Thorium Fuels, Part 2

The status of aqueous processing methods for tharium fuels is reviewed. A specially designed 250-ton shear was successfully tested for shearing full-size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths.
Date: June 7, 1963
Creator: Blanco, R. E.; Ferris, L. M.; Watson, C. D. & Rainey, R. H.
System: The UNT Digital Library
Maritime Loop Irradiation Program for Savannah I Fuel Post-Irradiation Examination of SI5BM Fuel Assembly (open access)

Maritime Loop Irradiation Program for Savannah I Fuel Post-Irradiation Examination of SI5BM Fuel Assembly

Abstract: A stainless steel clad 9-rod assembly fabricated by The Babcock & Wilcox Company was irradiated in a boiling water loop of the General Electric Test Reactor. A post-irradiation examination revealed no significant dimensional changes on the fuel rods. the results of mass spectrometric analysis made of the pelletized UO2 fuel indicated a maximum burnup of 11,500 MWD/tonne was attained by Rod B-4 during the exposure.An x-ray diffraction examination of an unirradiated fuel sample revealed the presence of UN2 and U2N3 phases. Metallographic examination of the irradiated microstructures revealed similar second-phase particles.
Date: November 7, 1963
Creator: Mathay, P. W.
System: The UNT Digital Library
Fuel Cycle Program Progress Report: Thirteenth Quarter, July-September 1963 (open access)

Fuel Cycle Program Progress Report: Thirteenth Quarter, July-September 1963

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities
Date: October 7, 1963
Creator: Howard, C. L.
System: The UNT Digital Library
Studies of the Rapid Beam Ejector at the Cosmotron (open access)

Studies of the Rapid Beam Ejector at the Cosmotron

For an experiment to measure the magnetic moment of the Λ hyperon, it was necessary to extract the external beam of the Cosmotron with maximum efficiency and with minimum time duration. To accomplish this end, the standard external beam of the machine was supplemented with the Rapid Beam Ejector. It was found that, unfortunately, the ejection efficiency of the beam was less than normal when the RBE was used. Measurements of the ejection efficiency were made by irradiating polyethylene foils at the second focus of Beam 1 with 3 BeV protons. The external beam was tuned up and optimized in a standard manner. It was found that the ratio of the number of protons ejected with the RBE to the number ejected without the RBE was 0.3 in one run and 0.22 in another try. It was also observed that the RBE did not shift the position of the external proton beam focus to within ± 1/8 in.
Date: February 7, 1963
Creator: Barton, M. Q.
System: The UNT Digital Library
Refractive Indices and Densities of Aqueous Solutions of Invert Sugar (open access)

Refractive Indices and Densities of Aqueous Solutions of Invert Sugar

Report of the refractive indices and densities of aqueous solutions of invert sugar at temperatures of 15, 20, 25, and 30º C, for concentrations up to about 82 percent of invert sugar (by weight). From the results, equations have been derived which relate the refractive index and percent of invert sugar (weight in air) at each temperature. Other equations relate the absolute density and percent of invert sugar (weight in vacuum) at each temperature. Five-decimal tables giving the refractive indices and densities of invert sugar solutions containing 1 to 85 percent of sugar are given for each percentage of invert sugar at the four temperatures.
Date: June 7, 1963
Creator: Snyder, Carl F. & Hattenburg, Albert T.
System: The UNT Digital Library
[Report to J. E. Curry by H. M. Hart, December 7, 1963 #3] (open access)

[Report to J. E. Curry by H. M. Hart, December 7, 1963 #3]

Poor quality photocopy of a report to Chief J. E. Curry of the Dallas Police Department. The report, which was submitted by H. M. Hart, states that Mrs. Linda Jackson is the present manager of the apartment house where Jack Ruby lived. Her records indicated that he moved into the apartment in 1959 and moved out of the apartment in 1961. His sister, Eva Grant, lived with him during this time.
Date: December 7, 1963
Creator: Hart, H. M.
System: The Portal to Texas History
[Report from C. C. Wallace to Chief J. E. Curry, December 7, 1963] (open access)

[Report from C. C. Wallace to Chief J. E. Curry, December 7, 1963]

Report from C. C. Wallace to Chief J. E. Curry, concerning a second interview with W. J. Harrison. Wallace provides further information added to Harrison's report.
Date: December 7, 1963
Creator: Wallace, C. C.
System: The Portal to Texas History
[Report to J. E. Curry by H. M. Hart, December 7, 1963 #2] (open access)

[Report to J. E. Curry by H. M. Hart, December 7, 1963 #2]

Photocopy of a report to Chief J. E. Curry of the Dallas Police Department. The report, which was submitted by H. M. Hart, states that Mrs. Chloe Stansell was the manager of the apartment house where Jack Ruby lived from 1957 to 1959. Stansell said that there were no unusual incidents during the time that Ruby lived in the apartment. She had never seen Lee Harvey Oswald.
Date: December 7, 1963
Creator: Hart, H. M.
System: The Portal to Texas History
[Report to J. E. Curry by H. M. Hart, December 7, 1963 #2] (open access)

[Report to J. E. Curry by H. M. Hart, December 7, 1963 #2]

Report to Chief J. E. Curry of the Dallas Police Department. The report, which was submitted by H. M. Hart, states that Mrs. Linda Jackson is the present manager of the apartment house where Jack Ruby lived. Her records indicated that he moved into the apartment in 1959 and moved out of the apartment in 1961. His sister, Eva Grant, lived with him during this time.
Date: December 7, 1963
Creator: Hart, H. M.
System: The Portal to Texas History