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2,657 Matching Results
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Axial flux data for fuel measurement
A survey of the PITA-18 nonpoisonous spline program was conducted in conjunction with a study to determine the best method of eliminating the variability of axial flux on the fuel performance parameter, q. The results of this survey and the conclusions reached in the rupture coefficient study were found to be inter-dependent such that both are presented in this report. The data from the PITA-18 nonpoisonous spline program, as received, is the output of the NOLA-2 computer program. One quantity of interest is the rupture potential relative to a cosine, commonly referred to as the relative rupture potential. As programmed, the relative rupture potential, which was derived by applying the rupture model to individual fuel elements, might be expected to vary linearly with the rupture rate. The use of the relative rupture potential was studied over the period of July 1962 through December 1963. The results of this study are presented.
Date:
February 11, 1964
Creator:
Popovich, R. P.
Object Type:
Report
System:
The UNT Digital Library
Loading and operating conditions for charge of five NIE-1 fuel tubes and two target assemblies in KER-1 or KER-2 Production Test IP-584-D, Supplement B
Production Test IP-584-D, Supplement B authorized the irradiation of target assemblies in KER-1 and KER-2. Furthermore, the production test authorized that these target assemblies be irradiated with)other approved production tests; for this test, N Reactor inner fuel elements (NIE-1) will be irradiated. The production test required that specific operating conditions and loading patterns would be approved by the managers of Testing, Process and Reactor Development, and Process Technology Subsections prior to charging.
Date:
May 25, 1964
Creator:
Deobald, T. L.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, July 1964
This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.
Date:
August 14, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Production test IP-665-A, evaluation of hot-die-sized end bonding processes
Investigations of possible operational limitations of the ALSi bonded e elements and the need for a replacement or alternate fuel fabrication process have been lender way for several years. Recently, one fuel manufacturing process, hot-die-sized diffusion bonding, has been intensely examined and irradiation testing of this new fuel type began in 1963. This production test is one additional step in evaluating the new fuel fabrication process. The objective of this test is to evaluate the effect end-bonding techniques on the irradiation behavior of hot-die-sized diffusion bonded fuel elements. Three types of fuel elements will be used in this test: (1) hot-die-sized diffusion bonded elements which have been end bonded by the resistance heating method; (2) hot-die-sized diffusion bonded elements which have been end bonded by the induction heating method; and (3) standard production AlSi bonded fuel elements. Twelve columns of fuel containing the three element types alternated throughout the columns will be irradiated in the test. Twelve smooth-bore Zircaloy-2 process tubes in the C Reactor will be utilized for this test; consequently, all fuel elements of this test are self-support models. These fuel columns will be irradiated to average exposures of 800 Mwd/t. Examination and measurement of the elements of …
Date:
March 30, 1964
Creator:
Hladek, K. L.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Department Monthly Report: May 1964
This report, for May 1964 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; employee relations; and weapons manufacturing operation.
Date:
June 22, 1964
Creator:
Hanford Atomic Products Operation. Chemical Processing Department.
Object Type:
Report
System:
The UNT Digital Library
Fuel element development committee: Annual report from the General Electric Company, Hanford
A summary of HAPO activities is given to include separate sections on the N-Reactor and other current production reactors. Specific programs and fuel performance for current production reactor fuels is discussed. Also, the production status, fuel performance, development program and process technology for N-Reactor fuels is presented.
Date:
August 14, 1964
Creator:
Lewis, M.; Minor, J. E. & Stringer, J. T.
Object Type:
Report
System:
The UNT Digital Library
Technical bases, U-233 production study Group IV-A
None
Date:
June 24, 1964
Creator:
Woods, W. K.
Object Type:
Report
System:
The UNT Digital Library
Modified tubular support patterns: Ribbed and ribless process tubes
Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to use tubular dummies for this portion of the support charge which are less expensive to fabricate and which are easily identified during the charging-discharging process. However, there exists a remote possibility that one or more tubular pieces could be inadvertently placed in a rear nozzle resulting in a flow restriction in the process tube. These arrangements of tubular support pieces in the dummy pattern, i.e., tubulars positioned against the fuel column and/or in the process tube rear nozzles, have been hydraulically tested to determine if there is adequate and unrestricted flow at normal operating header pressures.
Date:
August 25, 1964
Creator:
Angle, C. W.
Object Type:
Report
System:
The UNT Digital Library
End closure of hot die size diffusion bonded fuel elements
Studies initiated at Hanford in 1961 for the purpose of developing an alternate cladding process for I&D fuel elements for the eight existing production reactors indicated that the hot die sizing diffusion bonding process offered the greatest incentive. Hot die sizing was the most attractive with respect to improved fuel quality and potential reduction in fuel element unit cost when compared to the existing AlSi brazing process. Initial development work consisted of determining optimum process parameters for producing good diffusion bonds on the inner and outer lateral surfaces during sizing. This report summarizes the results of a series of end bonding variables tests designed for producing good diffusion bonds on the ends of hot die sized fuel elements.
Date:
January 14, 1964
Creator:
Strand, C. A.
Object Type:
Report
System:
The UNT Digital Library
Effects of Hanford Operations on Columbia River temperatures: Interim report No. 2
A research and development project for study of the effects of reactor effluent on Columbia River water quality is being sponsored by the AEC Division of Production. Work was started in October 1962, the first effort being aimed at furnishing an immediate answer to a security question: how closely can Hanford production be estimated by measurement of river temperatures? An interim progress report gave the results of the preliminary investigation. During the calendar year 1963, the study was expanded to meet broader program objectives. This document is a progress report for the year, covering the temperature and effluent distribution phases of the program. Progress on the chemical characteristics phase of the program is documented separately. Figure 1 shows the section of the river under study.
Date:
December 3, 1964
Creator:
Corley, J. P.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, March 1964
The monthly report for the Hanford Laboratories Operation, March 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operation, and programming operations are discussed.
Date:
April 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
241-SX tank farm waste storage
Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total of 12.1 Kgs of the 29.1 Kgs of Np-237 estimated has been recovered or is present in the Redox Np-237 accumulation cycle as of 4-30-64. Because of the potential for unmeasured losses (such as Pu or U precipitates) the total plutonium and uranium may exceed the quantities stated herein. A breakdown of the estimates by tanks is provided.
Date:
September 3, 1964
Creator:
Hanson, G. L.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, August 1964
The monthly report for the Hanford Laboratories Operation, August 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.
Date:
September 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Production Test IP-584-D, supplement B, irradiation of target assemblies in the KER Loops
The objective of this supplement to Production Test IP-584-D is to authorize low exposure (5--8 GVR) irradiation tests of the following lithium-containing target materials: Magnesium -- 14 percent lithium alloy, Lithium-aluminate (LiA1O2), Lithium-silicate (Li2SiO), Lithium-aluminate -- aluminum cermet, Lithium-silicate -- aluminum cermet. Lithium target materials will be contained in 4.50 inch long aluminum cans which are clad with 35 mil Zircaloy-2 alloy. The target elements will be contained in 1.9 inch OD, 1.5 inch ID Zircaloy-2 flow distributing sleeves. The target element assemblies and N Reactor inner-fuel elements (NIE-1) in Zircaloy-2 sleeves, will be irradiated in KER-1 or KER-2 at operating conditions approximating N Reactor operation.
Date:
April 28, 1964
Creator:
Deobald, T. L.
Object Type:
Report
System:
The UNT Digital Library
PT IP-603-I, Evaluation of accidental fuel flushing potential D-DR reactors. Final report
The purpose of Production Test IP-603-I described in this report was to obtain data to help determine if uranium I&E fuel can be flused from tubes set up for discharge on a valved down corssheader by raising the front riser pressure. The test consisted of valving down one header at shutdown riser pressure, then increasing the riser pressure and recording the resulting front nozzle pressures on selected tubes uncapped on the rear. Test results and conclusions are presented.
Date:
March 18, 1964
Creator:
George, D. K. & Hollifield, P. J.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, October 1964
The monthly report for the Hanford Laboratories Operation, October 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operations are discussed.
Date:
November 16, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Investigation Report H Reactor Mischarging Incident. Revision 1
This document provides details of the investigation of the H Reactor mischarging incident.
Date:
May 1, 1964
Creator:
Vinther, A. P.
Object Type:
Report
System:
The UNT Digital Library
An evaluation of the experimental determination of the effects of burnout and corrosion on spline worth
Efforts have been made to experimentally evaluate and to calculate the effect of reactor environment on splines. This report follows some of these efforts and relates them to operational experience. The use of splines in the Hanford Reactors has improved the efficiency and ease of operating the reactors. With the widespread use of splines, it is important to know the effect of reactor exposure to safely and efficiently use the splines in reactor operation.
Date:
July 13, 1964
Creator:
Blyckert, W. A.
Object Type:
Report
System:
The UNT Digital Library
Neptunium-237 production forecasts, IPD 1964--73
Neptunium-237 production has been-calculated according to the equations documented in Reference 1 for use in 1964-AEC study. cases. The assumptions made in the forecasts are as follows: Only the 947 stream is recycled. The blend enrichment for the recycle maternal is 1.2 per cent for F-Y 64 and 65. For FY 66 -73, a blend enrichment of 1.4 per cent is assumed which is better value according to the optimization model of C. W. Showalter. The 947 stream recycle time is two years. In cases A and B where the 947 stream volume is materially increased, virgin 947 material is introduced to make up the material balance. The U-236 content of the blend material- is 66 ppm{sup 2}. The U-236 input level in the 947 stream for the input of FY 64 is 200 ppm{sup 1}. Separations recovery is 85 per cent for FY 64--65 and 90 per cent thereafter. The material throughput data are given in Table I. These values are consistent with those being assumed for the AEC study cases. The Kgs of Np-237 by fiscal year are given in Table II. It must be remembered that these forecasts are based on a particular set of idealized assumptions, …
Date:
July 10, 1964
Creator:
Nilson, R.
Object Type:
Report
System:
The UNT Digital Library
Final report B, D, F reactor side shield hole boring technology
Four years of intermittent development has culminated in the successful test drilling on-reactor, of one step plug hole. Since 1960, several different drive units and many diamond, carbide, and tool steel cutting heads were tried unsuccessfully in attempts to bore a stepped hole in a mockup of B, D, P side shielding. Success was finally achieved in 1963 using a standard horizontal boring mill and tool steel cutters. With slight modifications, this same equipment was successfully used in an on-reactor test drilling at F Reactor in December of that year. The on-reactor test revealed the need for improvements in the equipment. Chip flow was inadequate and appeared to be caused by poor air flow in the core receiver. Cast iron cutting technology used on the mockup did not work on-reactor and had to be revised on the spot. The graphite did not break up into chunks as desired and had to be manually removed. None of the steel cores were more radioactive than 50 mr/hour at approximately 2 inches, but the cast iron core read 300 mr/hour at 10 feet. It had to be handled very quickly. The dose rate for handling the graphite was 400 mr/hour. It, too, was …
Date:
February 3, 1964
Creator:
Clemans, W. H.
Object Type:
Report
System:
The UNT Digital Library
Capsule irradiation of uranium with low alloy additions
Here is a more complete description of the capsule test we discussed in our initial contact in December. I have included as much detailed description of the test as has been decided on to date. Also, there are some factors which, from previous similar test, I have found to be pertinent to the successful charging and irradiation performance of the capsules. There is one critical point that needs to be settled as soon as possible. In order to finish machining the outer diameter of the capsules, the expected approximate specific power generation and enrichment in the surrounding process tubes must be known. In addition, there are several other factors which effect the location of the test in the reactors which Bob Marshall and I would like to go over with one of hour engineers as soon as possible.
Date:
January 16, 1964
Creator:
Weber, J. W.
Object Type:
Report
System:
The UNT Digital Library
Technical note on results of production test IP-628-AI: Crosstie flow test and flushing calibration, and the earlier production tests IP-573-AI and IP-499-AI
A series of three experimental tests was conducted on the operation and adequacy of the K-Reactors` third, or last-ditch, cooling system. The first test showed considerable line corrosion the second test was performed directly after line cleaning, and the third test showed a significant amount of additional line corrosion after only nine months of service. The present cooling adequacy of this last-ditch system at the KE and KW reactors is summarized these show the power levels for which we have adequate last-ditch cooling as a function of the crosstie coolant temperature. These figures include the effects of increasing the number of pumps that remain in operation at the other K-Reactor, and various other operating or emergency conditions. These curves are for diesel pump speeds of 750 rpm which are planned for June of this year. In these figures the crosstie temperature is assumed to be a conservative 5{degrees}C above the process water inlet temperature.
Date:
June 15, 1964
Creator:
Jones, S. S.
Object Type:
Report
System:
The UNT Digital Library
Irradiated Fuel Age Determination Study
The release of uncontrollable quantities of harmful fission products such as I{sub 131} upon processing areas. At present this is done by procedural techniques using cards, filing techniques, and cross checks. These methods are entirely independent of the characteristics of the fuel itself and are subject to failure from human error. It is therefore advantageous to find a method of determining the age of irradiated fuel after discharge from the properties of the fuel. Such a method, with its relative immunity to human error, would be very useful in checking shipments as well as for such jobs as determining the correct age of fuel being stored for accumulation of desirable fission product daughters. It was the purpose of this effort to make a study of possible methods of direct fuel age determination, formulate and perform a test of the most promising method, and analyze the results in terms of practicability here at Hanford.
Date:
August 31, 1964
Creator:
Cooley, D. E.
Object Type:
Report
System:
The UNT Digital Library
Hanford Laboratories monthly activities report, November 1964
This is the monthly report for the Hanford Laboratories Operation, November 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research.
Date:
December 15, 1964
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library