Evidence for Subshell at N = 152 (open access)

Evidence for Subshell at N = 152

None
Date: May 6, 1954
Creator: Ghiorso, A.; Thompson, S. G.; Higgins, G. H.; Harvey, B. G. & Seaborg, G. T.
System: The UNT Digital Library
Carbon Dioxide Fixation by Rhodopseudomonas Capsulatus (open access)

Carbon Dioxide Fixation by Rhodopseudomonas Capsulatus

This report is about the study of mechanism of carbon dioxide fixation by the non-sulfur purple bacterium, Rhodopseudomonas, capsulatus.
Date: October 6, 1954
Creator: Stoppani, A. O. M.; Fuller, R. C. & Calvin, M.
System: The UNT Digital Library
MEETING XV -- BEVATRON RESEARCH CONFERENCE -- BEVATRON STATUS (open access)

MEETING XV -- BEVATRON RESEARCH CONFERENCE -- BEVATRON STATUS

On April 1, a new energy peak of 6.1 Bev was attained with the Bevatron. Scattered particles monitored with a counter telescope in triple coincidence gave approximately 100 counts per beam pulse. April 2s the machine was down to air to allow work on beam monitoring equipment. Test operations resumed April 5. Though the total number of accelerated particles is still small, due to low energy beam losses, some cloud chamber tracks have been observed. Several plates have been exposed for Goldhaber. Stars with up to 29 prongs have been observed. The following consists of a discussion of the administration, operation and some of the experimental techniques evolved in the use of the Cosmotron.
Date: April 6, 1954
Creator: Lofgren, E.J.
System: The UNT Digital Library
Bevatron Research Meeting I  - Bevatron as a Research Instrument (open access)

Bevatron Research Meeting I - Bevatron as a Research Instrument

The Bevatron status is: (1) Physical structure of magnet now assembled and being tested. Initial pulsing to rated field currents indicate that magnet is performing as designed. Currents of the order of 8500 amps peak have already been rendered. (About 15,000 gauss). (2) Pumpdown time to approximately 10{sup -5} mm Hg is of the order of 24 hours at present but is expected to improve to 12-15 hours as the high vapor pressure solvents are removed. Lofgren and Brobeck expect that it will be possible to make interval target, etc., changes between operating shifts without excessive loss of experimental time. (3) Injector and linear accelerator are now operating stably. Injected currents to Linac are approximately 3 x 10{sup -3} peak at 450 kev. Linac output is approximately 5% or 70 x 10{sup -6} amps peak with an angular divergence of 10{sup -3} rad. and a maximum energy spread of less than 0.8% at 9.8 kev. (4) Inflector and induction electrodes are to be installed after December 15, 1953. (5) Complete machine, both mechanical and electrical, will be ready for testing and 'de-bugging' approximately December 15; 1953. Initial operation as a research instrument should begin after the first of the year, …
Date: October 6, 1953
Creator: Lofgren, Edward
System: The UNT Digital Library
The Preparation of Large-Diameter Zirconium Crystal Bar by the De Boer Process (open access)

The Preparation of Large-Diameter Zirconium Crystal Bar by the De Boer Process

None
Date: March 6, 1951
Creator: Bulkowski, H. H.; Beale, L. C.; Sebenick, J. J.; Campbell, I. E. & Gonser, B. W.
System: The UNT Digital Library
PRESSURE DROP THROUGH BEVELLED MULTIHOLE ORIFICES IN SERIES. (PWR Blanket Design) (open access)

PRESSURE DROP THROUGH BEVELLED MULTIHOLE ORIFICES IN SERIES. (PWR Blanket Design)

The continuation of a study of pressure drop across various combinations of staggered multihole orifice plates in series is described. Plates used in this test contained bevelled leading edge holes and were of the general design proposed for fiow control in the PWR blanket region. Variables examined in this test were orifice diameters of 0.300, and 0.625 in., one to six plates in series, and flow rates corresponding to orifice Reynold's numbers ranging from 15,000 to 140,000. The orifice plates and experimental methods employed in this test were similar to those described in the preceding orifice plate report. WAPDTH-241 (41 holes on a 0.486 in. square pitch located in a 4.195 in. diameter pipe), with the exception that the present plates had a 3O deg bevel around the leading edge of each hole sufficient in depth to make the bevelled diameter 1/16 in. larger than the hole diameter. Results are given as pressure loss coefficients (number of orifice velocity heads), and were found to be about 50% less than comparable values for squarc edge orifices. In general, Reynolds's number had no effect upon the loss coefficients. The loss coefficients are estimated to be accurate within plus or minus 10% over …
Date: December 6, 1956
Creator: Quandt, E.R. Jr. & LeTourneau, B.W.
System: The UNT Digital Library
Improvement of the hydrogen fluoride gas delivery system in the 234-5 Building (open access)

Improvement of the hydrogen fluoride gas delivery system in the 234-5 Building

The primary purpose of this report is to set forth the reasons why the Task II hydrogen fluoride gas delivery system is unable to supply sufficient quantities of the gas to the process at all times and to make recommendations on how to correct this problem. However, it is also a secondary purpose of this report to make general recommendations on all phases of the gas delivery system where it is felt that an improvement can be made in either the design or operation of the system.
Date: October 6, 1954
Creator: Swain, E.O.
System: The UNT Digital Library
DENSITIES AND BOILING POINTS OF URANYL NITRATE-NITRIC ACID SOLUTIONS (open access)

DENSITIES AND BOILING POINTS OF URANYL NITRATE-NITRIC ACID SOLUTIONS

The intercycle evaporators in the Chemical Processing Plant are controlled by density-measuring instruments. Because of difficulties in controlling these evaporators in a satisfactory manner, a series of investigations was begun to measure the boiling points at the elevation of the CPP, and densities near boiling temperatures of a number of solutions in the uranyl nitrate-nitric acid-water system. From these data it was hoped to evaluate temperature sensitve devices as controllers for the evaporators.
Date: May 6, 1953
Creator: Perkins, R.H.
System: The UNT Digital Library
RADIATION TESTING OF SHIELD SPECIMEN: TEST LTH/sub x/-4. (open access)

RADIATION TESTING OF SHIELD SPECIMEN: TEST LTH/sub x/-4.

None
Date: January 6, 1958
Creator: Lee, R.C.
System: The UNT Digital Library
Hazards Summary Report for the Walter Reed Army Medical Center Nuclear Research Reactor (open access)

Hazards Summary Report for the Walter Reed Army Medical Center Nuclear Research Reactor

Detailed descriptions are given concerning the reactor design, operation, location, and the using agency. Potential hazards are evaluated along with safeguards. A supplement is included which further describes the reactor core. (J.R.D.)
Date: May 6, 1959
Creator: Cappel, H.H.
System: The UNT Digital Library
A shaped charge system for well casing perforating (open access)

A shaped charge system for well casing perforating

Water wells drilled in the Hanford Works area for water quality monitoring, water level determination and geologic information demand use of steel casing. This casing is required due to the inability of the unconsolidated sediments penetrated by the well to stand without support. It is obvious that openings in the casing must be provided to permit free communication with the water bearing formation if the well is to be useful for water quality determination, aquifer testing and water level information. A shaped charge system originally designed for oil well squeeze cementing was adapted for non-routine re-perforating of Hanford water wells. Ten-gram shaped charges developed by Jet Research Center, Arlington, Texas are utilized. The charge carrier is a special 5`` diameter, 5` long heavy-wall steel tube. This carrier or gun is so designed that in each plane of shots there are four horizontal charges placed at 90{degree} angles. These shot planes are placed 3`` apart and successive shot planes are phased at 45{degree} angles with respect to each other. A maximum of 16 perforations per foot may be made and a maximum of four feet perforated with one carrier. Tandem or multiple runs may be made if greater length and density …
Date: October 6, 1958
Creator: Raymond, J. R.
System: The UNT Digital Library
Preliminary BPX flowsheet (open access)

Preliminary BPX flowsheet

Current H.A.P.O. planning has scheduled significant increases in low-NGS irradiated fuel production for the near future. This action, coupled with the imminent activation of the K-Reactor areas, will result in a uranium production rate which exceeds the anticipated capacities of the Purex, Redox and T Plant separations facilities. Additional separations capacity is scheduled to be provided by reactivating B Plant. However, a number of other separations processing schemes -- which will provide additional capacity -- are being evaluated for their economic and operating attractiveness as compared to combined BiPO4-TBP plant operation. The BPX process described in this memorandum is one such process. It is a modification of the TBX Scheme III of HW-32691. BPX was first proposed by the Manufacturing Department in HW-32908. The pertinent flowsheet details of the BPX process are provided and a discussion elaborates on the novel features of the flowsheet and also lists process items of general technical interest.
Date: October 6, 1954
Creator: Platt, A. M.
System: The UNT Digital Library
Production Test No. 105-530-A, Supplement B: New methods of fabricating horizontal control rods (open access)

Production Test No. 105-530-A, Supplement B: New methods of fabricating horizontal control rods

This memorandum discusses procedures to test new methods of bonding boron to aluminum tubing in the fabrication of horizontal control rods.
Date: March 6, 1953
Creator: Hulin, M. W.
System: The UNT Digital Library
A plant weekly summary---Purex operation, January 6, 1958--December 29, 1958 (open access)

A plant weekly summary---Purex operation, January 6, 1958--December 29, 1958

This report contains the weekly summaries for the Purex process at the Hanford Engineer Works for January 6, 1958 to December 29, 1958. Each summary includes uranium production, maximum operating rate, and waste loss statistics as well as an operating experience briefing. (JL)
Date: January 6, 1958
Creator: Schroeder, O. C.
System: The UNT Digital Library
Safety Experience: Reactor and Critical Facilities (open access)

Safety Experience: Reactor and Critical Facilities

This document provides a discussion of reactor safety of the Hanford production reactor and critical facilities. A description of each facility is provided and details of significant safety incidents are provided.
Date: May 6, 1955
Creator: Greager, O. H.
System: The UNT Digital Library
Eisenhower slugs (open access)

Eisenhower slugs

None
Date: November 6, 1952
Creator: Mars, H. L.
System: The UNT Digital Library
Removal of ruptured slug from tube No. 3486-H (open access)

Removal of ruptured slug from tube No. 3486-H

None
Date: July 6, 1951
Creator: Hubbard, E. T.
System: The UNT Digital Library
Water requirements at 105-K immediately following an electrical outage (open access)

Water requirements at 105-K immediately following an electrical outage

The purpose of this report is to specify the water flow rates and pressures which must be maintained at the process unit immediately following a Bonneville electrical power failure.
Date: June 6, 1952
Creator: Sege, C. & Locke, G. L.
System: The UNT Digital Library
Fuel Purge Pump Cooler Performance Test HRT Test No. II. A 68 a and b (open access)

Fuel Purge Pump Cooler Performance Test HRT Test No. II. A 68 a and b

None
Date: June 6, 1957
Creator: Frech, D. F.
System: The UNT Digital Library
Minutes of Meeting Held at ORNL November 27, 1956 on the APPR-1 Control Rod Irradiation Program (open access)

Minutes of Meeting Held at ORNL November 27, 1956 on the APPR-1 Control Rod Irradiation Program

None
Date: December 6, 1956
Creator: Leitten, C. F. Jr.
System: The UNT Digital Library
Hazards summary report -- Projects CG-558 and CG-600 reactor plant modifications. Volume 1, Revision (open access)

Hazards summary report -- Projects CG-558 and CG-600 reactor plant modifications. Volume 1, Revision

The scope of projects CG-558 and CG-600, a discussion of reactor hazards, a technical summary of pertinent aspects of reactor control and reactor cooling, and a discussion of development programs designed to increase efficiency of operation and further decrease the hazards are included in this document Volume 1 of this report.
Date: March 6, 1957
Creator: Trumble, R. E.
System: The UNT Digital Library
ANP Chemistry Section Progress Report for April, 1956 (open access)

ANP Chemistry Section Progress Report for April, 1956

This report addresses the progress report of ANP chemistry for April 1956.
Date: June 6, 1956
Creator: Cuneo, D. R.
System: The UNT Digital Library
200 Area weekly report (open access)

200 Area weekly report

None
Date: October 6, 1955
Creator: Christl, R. J.
System: The UNT Digital Library
Oak Ridge National Laboratory Status and Progress Report September 1959 (open access)

Oak Ridge National Laboratory Status and Progress Report September 1959

None
Date: October 6, 1959
Creator: unknown
System: The UNT Digital Library