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An Improved Nuclear Density Gauge : Covering the Interval of July 1 to August 1, 1959
The following document is a note describing the building process of an improved nuclear density gauge in comparison to previous gauges, within the interval of July 1 to August 1, 1959.
Date:
August 7, 1959
Creator:
Burgwald, G. M.
System:
The UNT Digital Library
An Improved Nuclear Density Gauge : Quarterly Report No. 1 Covering the Period from June 1 to September 1, 1959
This report discusses the concept of an improved mass gauging technique with a scintillation counter as the radiation detector in order to meet industrial requirements.
Date:
October 8, 1959
Creator:
Burgwald, G. M. & Stone, C. A.
System:
The UNT Digital Library
An Improved Nuclear Density Gauge : Covering the Interval from September 2 to October 1, 1959
The following document is an updated note on the process of building an improved nuclear density gauge within the time interval of September 2 to October 1, 1959.
Date:
October 12, 1959
Creator:
Burgwald, G. M. & Stone, C. A.
System:
The UNT Digital Library
An Improved Nuclear Density Gauge : Quarterly Report No. 2 Covering the Period from September 1 to December 1, 1959
This report is the second in a series of quarterly reports on the discussion and progression of an improved nuclear density gauge, covering techniques measuring detector sensitivity to result in improved stability.
Date:
1959
Creator:
Burgwald, G. M. & Stone, C. A.
System:
The UNT Digital Library
Blast biology: a study of the primary and tertiary effects of blast in open underground protective shelters. Project 33. 1 of Operation Plumbbob
Dogs, pigs, rabbits, guinea pigs, and mice were exposed to nuclear detonations in two open underground partitioned shelters. The shelters were of similar construction, and each was exposed to separate detonations. Each inner chamber filled through its own orifice; thus four separate pressure environments were obtained. An aerodynamic mound was placed over the escape hatch of each structure to determine its effect on the pressure-curve shape inside the chamber. In one test a sieve plate bolted across the top of the mound was evaluated. Wind protective baffles of solid plate and of heavy wire screen were installed in the shelters to compare primary and tertiary blast effects on dogs. The shelters also contained static and dynamic pressure gages, radiation detectors, telemetering devices, and, in one test, air-temperature measuring instruments, dust-collecting trays, and eight pigs for the biological assessment of thermal effects. One dog was severely injured from tertiary blast effects associated with a maximal dynamic pressure (Q) of 10.5 psi, and one was undamaged with a maximal Q of 2 psi. Primary blast effects resulting from peak overpressures of 30.3, 25.5, 9.5, and 4.1 psi were minimal. The mortality was 19% of the mice exposed to a peak pressure of …
Date:
February 1, 1959
Creator:
Ricmond, D.R.; Taborelli, R.V. & Bowen, I.G.
System:
The UNT Digital Library
1024 Channel Time-of-Flight Analyzer for MTR Fast Chopper - Operating Manual
Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.
Date:
March 11, 1959
Creator:
Petree, F. L.
System:
The UNT Digital Library
Proceedings of the Sixth Tripartite Instrumentation Conference, Part 3: System and Component Reliability
Collection of papers presented during the third session (Tuesday, April 21, 1959) at the 6th Tripartite Instrumentation Conference. The five papers describe reliability, maintenance, and failure of electronic equipment and other components in reactors at Chalk River (Canada), Harwell (U.K.), and Oak Ridge (U.S.).
Date:
June 1959
Creator:
Woolston, J. E. & Townsend, S. J.
System:
The UNT Digital Library
Solid State Division Quarterly Progress Report: August 1952
This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date:
January 30, 1959
Creator:
Billington, D. S. (Douglas S.) & Howe, J. T.
System:
The UNT Digital Library
Chemical Processing Department Monthly Report: January 1959
This report for January 1959, 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:
February 20, 1959
Creator:
Hanford Atomic Products Operation. Chemical Processing Department.
System:
The UNT Digital Library
Linear Accelerator for Heavy Ions
The following report discusses the construction of two heavy-ion linear accelerators, one at the the University of California Radiation Laboratory and the other at Yale University. The goal for these accelerators is to produce ions of masses up to that of neon with energies of 10 Mev per nucleon.
Date:
March 27, 1959
Creator:
Wells, Don
System:
The UNT Digital Library
Existing reactor expansion study basis
The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it is necessary that a study program be undertaken to determine in general terms the plant changes required to support these forecasted levels, to evaluate the economic and technical feasibility of achieving the process conditions, and to present an integrated program for achieving these objectives. This study program will necessarily consider the interrelated effects of a number of various facets of reactor and water plant process conditions, operational requirements, and proposed development programs. The purpose of this document is to present a plan for the execution of the proposed study. Included in this outline are a review of the basic study considerations, problem assignments and schedules, and manpower and cost estimates for the performance of the …
Date:
June 24, 1959
Creator:
Heacock, H. W.
System:
The UNT Digital Library
Definitive process design, Redox multi-purpose dissolver installation
This document provides the required definitive scope design for dissolver equipment capable of nuclear safe processing by geometry of E-Metal and certain other fuels enriched to a maximum of one per cent U-235 equivalent. Using only a single dissolver installation of this design, it will be possible to process the current E-Metal monthly commitment in less than two weeks (five-day week). The proposed dissolver system is to incorporate design flexibility required to permit conversion to Zirflex processing of NPR fuels.
Date:
May 6, 1959
Creator:
Gustafson, L. D.
System:
The UNT Digital Library
Waste disposal criteria existing reactor expansion study
This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bulk outlet temperature limit is 105{degrees} or higher. For reactor flow rates exceeding 100,000 gpm it may be necessary to reduce sodium dichromate concentrations as low as 1.5 ppM during periods of low river flow. Heat output was discussed but no limit was set.
Date:
November 17, 1959
Creator:
Hall, R. B.
System:
The UNT Digital Library
Temperature Measurement in Operating Reactors: In-Reactor Temperature Measurement Associated With Fuel Element Testing
The Fuel Development operation at Hanford uses a variety of in-reactor facilities to test experimental and prototypical fuel elements. High pressure-high temperature water loops in constant use are the 6 in. {times} 9 in. ETR core facility, the 3 in. {times} 3 in. ETR reflector facility and four front-to-rear loops in the 100-K East reactor at Hanford. Low pressure water cooled test facilities in use are located in the MTR the various Hanford reactors. Stainless steel sheathed the thermocouples 1/16-inch diameter insulated with MgO or Al{sub 2}O{sub 3} when properly fabricated and installed, will reliably measure in-reactor temperature up to 1000 C and at least 4000 MWD/T exposure. This report provides a brief description of some of the temperature monitored in-reactor experiments.
Date:
December 9, 1959
Creator:
Wheeler, R. G.
System:
The UNT Digital Library
Control aspects of Old Pile Expansion Program
None
Date:
November 3, 1959
Creator:
Simpson, D. E.
System:
The UNT Digital Library
Power rate meter response characteristics
Power rate of rise measuring instrumentation is being procured for all of the Hanford piles, and a prototype installation is now in service at D reactor. This instrumentation is expected to provide valuable assistance to the pile operator during the start-up rise to operating power; in order to best utilize the instrument, procedures and limits must be determined on the basis of the relationship between the flux rate of change and the instrument response. As with any measuring instrument, there is an inherent delay in the power rate meter circuitry; in addition there are greater delays associated with the beat capacity of the metal and water and the transit time of the cooling water. Furthermore, reactivity changes from rod withdrawal and metal coefficient draping are not instantaneous, and the flux is not a simple function of the reactivity changes. Because of the time lags involved the rate meter response cannot be identical to the actual flux rate of change; however, an exact solution for this response in terms of all of the variables would be inordinately complex. The purpose of this study is to show approximately the changes in power level or rate which might occur in practice relative to …
Date:
April 13, 1959
Creator:
Simpson, D. E.
System:
The UNT Digital Library
Scope design for conversion of Purex anion exchange prototype to a manufacturing facility
This document is a HAPO report dated January 23, 1959, and describes the plutonium tail-end anion exchange system, installed in Purex as a prototype unit. Although some modifications, those considered most needed, were made to the unit, additional changes and refinements were still needed to convert the prototype to a fully acceptable manufacturing facility. This document covers the scope design of these modifications. The purpose of this document is to provide scope design criteria for a project to convert the plutonium tail-end Purex Anion Exchange Prototype to a manufacturing facility.
Date:
January 23, 1959
Creator:
Gustafson, L. D.
System:
The UNT Digital Library
Radiometallurgical examination of PT-IP-221-A measurement of flow channel temperature in 7 rod cluster fuel element (RM-287)
Eight Zircaloy-2 jacketed, natural uranium seven-rod cluster elements were irradiated in a KER loop to determine flow channel temperature characteristics. One of the elements, which had 200 MWD/T exposure, was sent to the Radiometallurgy Laboratory for examination in April 1959. An outside rod of the cluster was sectioned and examined metallographically. No cracks or flaws were observed in the uranium cladding or bonding.
Date:
June 16, 1959
Creator:
Teats, R.
System:
The UNT Digital Library
PT-IP-269-A-FP, evaluation of the stability of cores from extruded tubes
If material received under this program is deemed acceptable for reactor charging, this test will authorize irradiation of fourteen monitor columns which shall be discharged at 200, 400 and 800 MWD/T to observe the performance of this material. This test shall run concurrently with irradiation of quantities up to 60 tons/month to be authorized separately.
Date:
November 2, 1959
Creator:
Hall, R. E.
System:
The UNT Digital Library
P.T.: IP-272-A-FP, Pilot test of self-supported fuel elements in ribless zirconium process tubes
Up to one hundred ribless zirconium process tubes are to be installed in C Reactor, and necessary reactor equipment modifications made to permit routine charging of these tubes with self-supported natural uranium fuel elements. This test authorizes continued loading in these tubes until authorized by process standards or until it is deemed impractical to convert C Reactor to this geometry.
Date:
August 27, 1959
Creator:
Hall, R. E. & Curtiss, D. H.
System:
The UNT Digital Library
PT-IP-280-A-FP, irradiation of alloyed dingot uranium fuel elements
The objective of this test is to authorize irradiation of pilot quantities of alloyed dingot uranium and to provide for monitoring of its performance. This test will authorize: (a) Charging of up to 50 tons of alloyed dingot fuel elements in two groups of 25 tons each, including 12 monitor charges which will accompany the first group, into D Reactor as a pilot loading. Although purer and ore dense than standard ingot uranium, the dingot uranium produced in the past by MCW has demonstrated poorer dimensional stability during irradiation. The instability has been manifest as warp, nearly double that of ingot which was irradiated in the same charge and by surface bumping up to 5 mils in height. Both the bumping and the warp are normally associated with large grain size, non-uniform orientation and/or residual stresses. To improve the stability,, primarily by grain size reduction, additions in the range of 150 ppm iron and 100 ppm silicon are being made to the green salt prior to reduction. The hydrogen content of the metal has been reduced by pre-heating the green salt at high temperature prior to triggering the metal reduction. Further refinements to the process include heat treatment in chloride …
Date:
October 10, 1959
Creator:
Hall, R. E.
System:
The UNT Digital Library
Technical basis for establishing process tube pressure limits for KER loops 2 and 3 and for the NPR Prototype Facility
In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.
Date:
June 26, 1959
Creator:
Adams, O. E.
System:
The UNT Digital Library
Single tube flow rates at low header pressures with nozzle caps removed: All reactors
Laboratory data of flow rate versus header pressure were obtained for various conditions of nozzle cap removal from C, K and BDF single tube mockups of central zone tube assemblies using I&E slug charges. The data are presented. Suggestions are made for applying the data to DR and H reactors. In general, the effect of a pre-inserted support charge on the flow rate is small, especially with the front nozzle cap on. It should be noted that pre-insertion of an entire (117 inch long) support charge and subsequent front cap replacement is impossible in either a BDF tube with 34 fuel elements or a C tube with 32 fuel elements simply from a length standpoint.
Date:
November 20, 1959
Creator:
Waters, E. D.
System:
The UNT Digital Library
Chemical Processing Department Research and Engineering Operation Monthly Report, April 1959
This report discusses research and engineering work on the purex and redox processes at the Hanford Engineering Works in May, 1959. (JL)
Date:
May 8, 1959
Creator:
Hanford Atomic Products Operation. Chemical Processing Department.
System:
The UNT Digital Library