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2,279 Matching Results
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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.
Object Type:
Report
System:
The UNT Digital Library
Control aspects of Old Pile Expansion Program
None
Date:
November 3, 1959
Creator:
Simpson, D. E.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Flow conditions at outlet fittings of existing Hanford reactors
This report records the basis underlying the decision already reached to recommend a change of process tube fittings at B, D, F, DR and H reactors, and also proposes for consideration a change in the devices for monitoring effluent water temperature.
Date:
November 12, 1959
Creator:
McLenegan, D. W.
Object Type:
Report
System:
The UNT Digital Library
Supplement B to production test IP-226-A: Irradiation of enriched seven-rod cluster elements with twenty and thirty-mil Zircaloy-2 jackets
Six 1.6% enriched Zircaloy-2 jacketed seven-rod cluster elements with modified end supports and one Zircaloy-2 jacketed Pu-A1 seven-rod cluster element will be irradiated in KER Loop 1 to an exposure of about 4500 MWD/T.
Date:
August 13, 1959
Creator:
Kratzer, W. K.
Object Type:
Report
System:
The UNT Digital Library
Advantages of palmolive alternate
It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.
Date:
March 17, 1959
Creator:
Coppinger, E. A. & Merrill, E. T.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Department Control Study: Final report on the control of CPD product materials
The purpose of this report is to present the conclusions and recommendations obtained during the course of the CPD Control Study and the conceptual framework upon which they are based. Primary emphasis has been given to the control of product materials. In order to logically present the background for the definition and delineation of an appropriate CPD Control System, Section III of this report discusses a control system in the following manner; (1) the description of the control system information requirements, (2) the definition of the conceptual framework of product material control, (3) the discussion of the interrelationships of production scheduling, process control and accountability and (4) the methods for the effective utilization of control system information. Section IV utilizes this conceptual framework in order to enable a logical presentation of a proposed product material control system for the CPD. A summary of conclusions and recommendations is included in Section II. The Appendices consist of discussions of specific analysis conducted during the study. Other related reports that have been issued during the course of the study are included in the references.
Date:
January 5, 1959
Creator:
Shepard, D. F.; Hough, C. G.; Burke, R. C. & Stewart, K. B.
Object Type:
Report
System:
The UNT Digital Library
Design of production test IP-280-A-FP: Irradiation of alloyed dingot uranium fuel elements
Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 tons/ month may proceed for six months and, assuming continued favorable performance, up to 150 tons/month may be accepted to complete large scale evaluation of dingot uranium, and on a continuing basis thereafter.
Date:
August 28, 1959
Creator:
Hall, R. E. & Hodgson, W. H.
Object Type:
Report
System:
The UNT Digital Library
H Reactor enrichment
None
Date:
February 24, 1959
Creator:
Turner, R. L.
Object Type:
Report
System:
The UNT Digital Library
Palm content of production metal
Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.
Date:
November 23, 1959
Creator:
Campbell, M. H. & Swift, W. H.
Object Type:
Report
System:
The UNT Digital Library
Continuity of Operations Program: Prime Separations and Uranium Conversion Facilities
This Program detailed in this report is related to the Product Development, Palmolive, and Non-Production Fuels Programs under New and Special Products and Processes Category where the prime separations plants supply raw materials or processing support of these other programs. Likewise, Increased Plant Return Program items affecting the Purex, Redox, and UO{sub 3} Plants must be integrated with the Continuity of Operations Program. Since the primary separations plants feed the 234-5 Facility, the 234-5 Program is also related to Continutiy of Operation.
Date:
December 7, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Proposal for KER loop irradiation of coextruded defect test fuel specimens
Defect testing of the irradiated specimens will provide kinetic autoclave defect test data on the behavior and performance of coextruded Zr-2 clad fuel failures; this should reveal the effects of exposure on the coextruded U-Zr-2 bond.
Date:
December 16, 1959
Creator:
Goffard, J. W.
Object Type:
Report
System:
The UNT Digital Library
H pile axial flux distribution
Significant production gains could be made by improving metal rupture performance. A means of achieving this is by depeaking the axial flux distribution, thus reducing the maximum specific power for a given tube-power. The flux traverse program has provided some knowledge of front-to-rear flux, and was instrumental in prompting a change in the equilibrium HCR pattern during February, 1958. A ``before and after`` comparison of in-pile flux conditions is presented, and suggestions for further improvement are given.
Date:
March 23, 1959
Creator:
Gallagher, G. R.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: May 1959
This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.
Date:
June 15, 1959
Creator:
Hanford Laboratories
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories Operation Monthly Activities Report: February 1959
This is the monthly report for the Hanford Laboratories Operation, February, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection operation, and laboratories auxiliaries operation area discussed.
Date:
March 15, 1959
Creator:
Hanford Laboratories
Object Type:
Report
System:
The UNT Digital Library
Total Control vs Reactivity Parameters
Changes in pile operating parameters, such as fuel exposure, paver, and reactivity gain upon water loss affect the potential reactivity of the operating, pile and, therefore, the amount of enrichment required to operate under the desired conditions. Similarly a change in ECT (through enrichment location) changes the amount of enrichment.needed to maintain a constant reactivity. Many of the factors which influence the operating reactivity have quite different effects upon the reactivity of the dry pile with the ball 3X system inserted; therefore, changes in operating parameters may cause sizeable changes in requirements for supplementary control to maintain sub-criticality in the dry pile. It is the purpose of this document to summarize these trends in disaster control requirements for the K piles. The trends are presented as graphs of supplementary control requirements against a single varying parameter. All other parameters are held fixed as specified on each graph. The fuel element (central orifice zone) for all examples is the K-2 slug. In general, the slopes of these curves are only slightly dependent upon the specific values assigned the fixed parameters, although the magnitude of the control requirements may be quite dependent on these values. Unless otherwise noted any dependence of the …
Date:
February 5, 1959
Creator:
Simpson, D. E.
Object Type:
Report
System:
The UNT Digital Library