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KER-3 Operating Report: Test No. K-3-10 -PT-IP 288-A, Test No. K-3-11 -PT-IP-317-A -PT-IP-315-A

Description: The loop was charged October 30, 1959 with seven 12-inch Natural Uranium Zircaloy-2 clad 7-rod clusters. The test was primarily for the new hot-headed method of end closure used on these elements. The loop was pressure tested at 4000 psi after it was charged. Initially the loop was held at low-temperature to study the buildup of oxygen (presumably from radiolytic decomposition of water). After startup the neutron activity held at slightly above normal but the strainer gamma activity was excepti… more
Date: July 13, 1960
Creator: Sharp, F. E.
Partner: UNT Libraries Government Documents Department
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Irradiation summary report - PT-IP-288-A, evaluation of seven rod cluster elements with modified end closures

Description: The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.
Date: July 13, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand characteristics of self-supported C-IV-N and K-I-N I&E fuel elements in a zirconium C-Reactor tube

Description: This report discusses the isothermal hydraulic demand characteristics were determined by laboratory experiment for full charges of self-supported I&E fuel elements in a zirconium process tube. Pressure drop, flow rate data, and the calculations of annulus-to-hole flow ratio are presented. For self-supported fuel elements, pressure drop does not vary with temperature as much as it dies for non-self-supported furl elements.
Date: January 13, 1960
Creator: Waters, E. D.
Partner: UNT Libraries Government Documents Department
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E-N load conversion ratios

Description: No Description Available.
Date: September 13, 1960
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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A High-Voltage Pulse Generator for Testing Dielectric Samples

Description: Abstract: The purpose of this report is to describe the problems inherent to general dielectric strength measurements, and to act as a guide in establishing a method for pulse dielectric strength measurements.
Date: July 13, 1960
Creator: Kelly, R. D.
Partner: UNT Libraries Government Documents Department
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Production test IP-377-A, Irradiation of N-Reactor inner fuel tubes in the KER Loops

Description: The objective of the production test detailed in this report is to evaluate the behavior of N-Reactor inner fuel tubes during irradiation in the KER Loops at conditions equivalent to those expected in the N-Reactor. Natural and .947% enriched Zircaloy-2 jacketed N-Reactor inner fuel tubes (NIN-1) and (NIE-1) will be irradiated in the KER Loops to exposures no greater than 3500 MWD/T. The elements have brazed end closures and Zircaloy-2 supports and are contained in Zr-2 flow distributing sleeve… more
Date: December 13, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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EUROCHEMIC ASSISTANCE: COMMENTS BY ICPP ON QUESTIONS FROM EUROCHEMIC

Description: Answers by ICPP personnel to questions asked by Eurochemic are given on a variety of subjects, including off-gas sampling systems, off-gas filtration, iodine evolution during fuel dissolution, and process cell contamination. Data are presented on the% of I/sup 131/ retained in waste solutions in the absence and presence of mercury. (D.L.C.)
Date: June 13, 1960
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
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Special requirements CG-791 tie-in B, D, DR, and F reactors

Description: This memorandum discusses coupling of the reactor exhaust system to the filter building, under Project CG-791, which will require diversion of the 105 Building exhaust air to two temporary stacks. The temporary stacks will be installed over each of two exhaust fans. The use of these temporary (short) stacks during the tie-in period (estimated at 8 to 16 days) could greatly aggravate radiological problems because of reduced dilution and of the reactor building exhaust air. Special operating requ… more
Date: June 13, 1960
Creator: Reid, R. W.
Partner: UNT Libraries Government Documents Department
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Synthesis and Fabrication of Refractory Uranium Compounds. Monthly Progress Report No. 10 for September 1 Through September 30. 1960

Description: Several synthesis experiments were carried out to provide a stock of U/ sub 3/Si/sub 2/, powders for fabrication of test specimens. Initial thermal- expansion characteristics were determined on U/sub 3/Si/sub 2/ bars. High densities were obtained in the preparation of UN bodies. Thermal-expansion tests were made on bars of UN with a high-density silicon carbide tube dilatometer in a flowing argon atmosphere. (W.L.H.)
Date: October 13, 1960
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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An Experimental Study of Vortex Flow for Application to Gas-Phase Fission Heating

Description: An experimental investigation into the gas dynamics of a jet-driven vortex tube for application of a cavity nuclear reactor to rocket propulsion has shown that viscous retardation of the vortex motion is severe, because of a high level of turbulence near the periphery. Based on the experience gained in this study, it is estimated that the achievement of vortex strengths sufficient for practical application will require the use of small diameter tubes with appreciable expenditure of power for re… more
Date: June 13, 1960
Creator: Keyes, J.J. Jr. & Dial, R.E.
Partner: UNT Libraries Government Documents Department
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Idaho Chemical Processing Plant Technical Progress Report for January- March 1960

Description: 9 > ? ( ing schedule included MTR, ETR, and other aluminum-type fuels that were processed through the TBP headend at 75 to 100% of flowsheet rates and through the Hexone second and third cycle extraction system at up to l5O% of flowsheet values, achieving an over-all recovery of 99.60%. In carrying out basic studies on aqueous zirconium processing, results obtained during the potentiometric titration of zirconium-fluoride-nitric acid solutions with sodium hydroxide were explained by a mechanism… more
Date: July 13, 1960
Creator: Slansky, C.M.; Warzel, F.M. & Bower, J.R. Jr. ed.
Partner: UNT Libraries Government Documents Department
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SPECIFICATIONS AND FABRICATION PROCEDURES FOR SM-1A CORE II NEUTRON ABSORBER SECTIONS

Description: The composite plates of the absorber section consist of compacts of europium oxide-- stainless steel clad with stainless steel by hot roll-bonding. Specifications are given to cover materials, dimensional and finish requirements, tests for quallfication of absorber plate fabrication, the conformance of fabrication procedure, and the manufacturing procedures. Drawings are also included. (M.C.G.)
Date: May 13, 1960
Partner: UNT Libraries Government Documents Department
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Maritime Reactor Waste Disposal Studies: Solidification of Ion-Exchange Resin With Portland Cement for Radioactive Waste Disposal

Description: A procedure is reported for the sea disposal. by fixation in concrete. of ion-exchange resins containing sorbed fission products and filtered corrosion products. The results of sea disposal of both treated and untreated resins is presented. For the fixation of nuclear-reactor-system demineralizer resin in cement, a mixture of 2 parts of cement, 1 part of resin, and 1 part of water was found to be optimum. A concrete block prepared by this receipt showed only 0.44% of the gross gamma activity le… more
Date: September 13, 1960
Creator: Holcomb, R. R.
Partner: UNT Libraries Government Documents Department
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NEUTRON DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1960

Description: Research efforts in neutron physics are reported in the areas of light- water-moderated reactors, new reactors for BSF and TSF, critical experiments, experimental nuclear physics, experimental reactor physics, reactor theory, shielding research, radiation detector studies, plasma physics theory, and theoretical nuclear physics. Separate abstracts were prepared for the seventy sections of the report. (W.D.M.)
Date: December 13, 1960
Partner: UNT Libraries Government Documents Department
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SPECIFICATIONS AND FABRICATION PROCEDURES FOR PM-2A CORE II CONTROL ROD FUEL ELEMENTS

Description: Specifications were prepared for control rod fuel elements for the Core Il of PM-2A. These stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub2/ were successfully used in powering the Army Package Power Reactor. The component, which consisted of sixteen composite fuel plates joined by brazing, was designed for radioactive service in pressurized water. Tests for qualification of fabrication procedures and specifications covening loading, mat… more
Date: May 13, 1960
Partner: UNT Libraries Government Documents Department
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STABILIZING EFFECTS OF OXIDE ADDITIONS TO URANIUM OXIDE

Description: An investigation of the stabilizing influence of oxide additions to uranium oxide was continued. These additions are employed to eliminate the phase transformation to U/sub 3/O?sub 8/ which occurs when UO/sub 2/ is exposed to an oxidizing environment at elevated temperatures and to reduce the volatility or transpiration losses of uranium oxide which become appreciable in air at temperatures in excess of 1200 deg C. The results show that CaO may be successfully employed in partial substitution f… more
Date: September 13, 1960
Creator: Wilson, W.B. & Gerds, A.F.
Partner: UNT Libraries Government Documents Department
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SPECIFICATIONS AND FABRICATION PROCEDURES FOR SM-1A CORE II CONTROL ROD FUEL ELEMENTS

Description: Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully employed in powering the Army Package Power Reactor. The component is designed for radioactive service in pressurized water and consists of sixteen composite fuel plates Joined into an integral unit or assembly by brazing. Specifications covering loading, materials, and processing are presented. A list of applicable drawings and the process flow diagram are included. (… more
Date: May 13, 1960
Partner: UNT Libraries Government Documents Department
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SPECIFICATIONS AND FABRICATION PROCEDURES FOR SM-1A CORE II STATIONARY FUEL ELEMENTS

Description: Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully employed in powering the Array Package Power Reactor (SM-1). The component is designed for radioactive service in pressurized water and consists of eighteen composite fuel plates joined into an integral unit or assembly by brazing. Specifications are presented which cover loading, mterials, and processing. A list of applicable drawings and a process flow diagram are in… more
Date: May 13, 1960
Partner: UNT Libraries Government Documents Department
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SYNTHESIS AND FABRICATION OF REFRACTORY URANIUM COMPOUNDS. Monthly Progress Report No. 11, November 1-November 30, 1960

Description: Batches of UC were synthesized for use in fabrication of specimens for physical property determinations. This synthesis was carried out with mixed loose powders in a graphite crucible. Two and one-half pound batches of UN were synthesized using a stainless steel boat and an Inconel muffle furnace. Three batches of U/sub 3/Si/sub 2/ were synthesized with particular emphasis on controlling the rate of the reaction by limiting the maximum temperature to 1500 deg C. In addition, determinations were… more
Date: December 13, 1960
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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