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An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date:
July 1963
Creator:
Jackson, C. N., Jr.
System:
The UNT Digital Library
Coagulant Aids as Filter Aids
The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date:
July 21, 1960
Creator:
Conley, W. R.
System:
The UNT Digital Library
Critical Tests for PRT Reactor
This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date:
July 1, 1960
Creator:
Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
System:
The UNT Digital Library
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date:
July 18, 1960
Creator:
Frederick, C. L. & Waldkoetter, G. L.
System:
The UNT Digital Library
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
The Hanford Isotopes Production Plant Engineering Study
Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date:
July 1963
Creator:
La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
System:
The UNT Digital Library
Integrated Radiological Instrumentation System Planning
In recognition of the need for an integrated system plan for future development requirements for radiological instrumentation, this information report was written to provide the initial step concerning such a planning. The report is to be considered a basic information analysis of the present in-use plant radiological instrumentation, of the instrumentation now undergoing active development, and of the future development work contemplated.
Date:
July 14, 1960
Creator:
Spear, W. G.
System:
The UNT Digital Library
Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple
Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date:
July 12, 1960
Creator:
Kosut, Bert S.
System:
The UNT Digital Library
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Date:
July 1965
Creator:
Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
System:
The UNT Digital Library
A Model of the PRTR Mark I Fuel Element for Heat Transfer Experiments
The purpose of this document is to describe the design and construction of a full-scale, electrically-heated model of a 19-rod PRTR fuel element for use in heat transfer experiments.
Date:
July 6, 1960
Creator:
Hammond, J. E.
System:
The UNT Digital Library
PCTR Measurement of EGCR Control Rod Worth
This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, very closely related to the measurement of k∞ for an ordinary lattice cell.
Date:
July 20, 1960
Creator:
Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
System:
The UNT Digital Library
Portable Radiation Instrumentation Standardization
This development work was undertaken to investigate and standardize scintillation detector and transistorized circuitry techniques in instruments used for detecting and measuring alpha and beta particles, gamma photons, and both slow and fast neutrons. At the present time, the standard radiation detection instrumentation used at Hanford employ vacuum-tube circuitry with typical detectors being ion chambers, G-M tubes, HF3 tubes, etc. The vacuum tubes require excessive battery power, and some of the circuits are adversely affected by humidity and temperature conditions.
Date:
July 1, 1960
Creator:
Spear, W. G.
System:
The UNT Digital Library
Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels
Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and decontamination can be performed in existing facilities once the fueks have been placed in solution form.
Date:
July 29, 1960
Creator:
Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
System:
The UNT Digital Library
PRTR Calandria Fabrication Report
The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and lists recommendations for improving the design and reducing the cost.
Date:
July 12, 1960
Creator:
Pedersen, L. T. & Kreiter, M. R.
System:
The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures
Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date:
July 1961
Creator:
Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System:
The UNT Digital Library
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study
Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Date:
July 1964
Creator:
Godfrey, W. L. & Benham, R. D.
System:
The UNT Digital Library
Standardization and Evaluation of Grain Size Test for Uranium Fuel
Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.
Date:
July 1964
Creator:
Spice, R. D.
System:
The UNT Digital Library
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes
Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date:
July 30, 1963
Creator:
Pessl, H. J.
System:
The UNT Digital Library
A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials
This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel element support-bearing surface materials.
Date:
July 5, 1960
Creator:
Weber, J. W.
System:
The UNT Digital Library