This document reflects our comments on the drawings and design information that we have received. It is therefore contingent upon the drawings and specifications which we have not as yet received from Vitro Engineering Company.

Verify that the multigroup code P1MG and its associated library yield, for a flat flux problem, the same few group constants as the MUFT fast constant code.

ABS>The Gauss-Jordan, Choleski, congruent transformation, and rank annihilation methods for inverting large symmetric positive definite matrices were compared. An attempt was made to consider the effects of both condition and order of the matrix to be inverted on the closeness of the computed inverse to the exact inverse. Each method was programmed in FORTRAN using only single precision arithmetic. Then the error indicators were computed using double precision arithmetic so that the latter calculation was not a limiting factor. It was found that any one of the methods is satisfactory for a well-conditioned least squares matrix of order 10-30. However, when the matrix becomes ill- conditioned then the Gauss-Jordan method appears to be clearly superior (at least for the matrices studied). Algorithms and FORTRAN subroutines for each method are presented. (auth)

This document describes a deviation from the "Test Program and Procedures for the 710 Critical Experiment Reactor Loading and Rod Calibrations," TM-63-1-702, which was made in accordance with ITS Standard Practice J80-81 on March 13, 1963. The deviation did not involve a significant change in the safety of the operation.

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At the request of the US Atomic Energy Commission, the General Electric Company has undertaken an engineering-study preliminary to the design and construction of a fission product heat source production plant at Hanford. This document presents proposed feed materials, product specifications, and the chemical flowsheet basis for the engineering study. A preliminary waste extraction chemical flow-sheet is included to illustrate the integration of the proposed production plant with the Hanford Waste Management Program.

Thesis submitted to University of Tennessee, Knoxville. Activities in a program to determine the wetting behavior of pure metals such as Au, Ag, Ge, Al, and Cu on solid Be are reported. Results of similar investigations of binary alloys such as Be--Ti, Be-Zr, and Be--Pd are also included. The contact angles of the molten metals on Be as a function of temperature, exposure time, and atmosphere were measured. The solid-liquid interfacial reactions occurring as a function of test temperature and atmosphere were investigated, and the liquid- vapor and internal surface tensions for those systems in which interfacial reactions did not appear to occur were calculated. (J.R.D.)

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This report details activities of the Irradiation Processing Department during the month of November 1963.

The purpose of this test was to evaluate the uranium swelling and distortion of coextruded Zr-2 jacketed tubular fuel elements operating at N Reactor environmental conditions but with considerably higher uranium temperatures than those occurring in normal N Reactor fuel. The test is expected to provide information useful in the design and analysis of single tube fuel elements for use in N Reactor.

The static and dynamic surface tension was measured for aqueous solutions of eleven surface-active agents for the purpose of studying the effect of surface tension upon boiling heat transfer. The surfactants were chosen from the Tween, Aerosol, and Hyonic series. Dynamic surface tension, at T = 90 deg C, was investigated by observing the volume and frequency for air bubbles forming from a submerged orifice. Static surface tension, at T = 100 deg C, was measured using a duNouy tensiometer. In all cases, the dynamic surface tension for solutions of these surface active agents was less than the value for pure water, greater than the static value for the same concentration, and was a smoothly decreasing function of concentration. (auth)

The current E-N demonstration program began during mid-November 1962 in the AlSi Shop. Man meetings and conferences were held prior to this time to determine various methods by which the ultimate quality of the uranium portion of an E-N load could be enhanced at the expense of the material yield, if necessary. As a result of these meetings, it was decided that a superior grade fuel element could be manufactured by raising or lowering, as the cause may be, certain limitations that were currently governing the normal ``F`` process production. The new limitations were presented in Process Work Request 116 (1962), and the program began with fuel lot KY-312-E on November 19, 1962.

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ABS>Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of small fuel displacements in a pool- type reactor; studies in nuclear safety of fuels outside reactors; release of fission products from out-of-pile reactor fuels; release of fission products in in-pile melting or burning of reactor fuels; characterization and control of accident-released fission products; fission-product evaluation; I/sub 2/ removal from oxidizing gases at high temperatures; attenuation of fissionproduct escape by intrinsic processes; nuclear safety pilot plant; nuclear safety information center; radiochemicalplant safety studies; and space safety. (J.R.D.)

Detailed measurements of performance and energy transfer were made on two highly instrumented cylindrical cesium thermionic converters with electrically heated tungsten emitters. The first converter, OC-4, which had a niobium collector, operated with an initial electrical output of 6.9 watts/cm/sup 2/. This output gradually degraded to a value of 4.6 watts/cm/sup 2/ after 1351 hr. These power values were measured at the electrodes for an average emitter temperature of 1 750 deg C, Converter OC-5, which had a molybdenum collector, has operated 260 hr to date, with a power output and efficiency of 11.1 watts/cm/sup 2/ and 16%, respectively, at an average emitter temperature of 1800 deg C. These operating data are compared with those for lower emitter temperatures below. Temperature Density Efficiency Energy values of the emitter electron cooling, collector electron heating, thermal radiation, and cesium conduction were calorimetrically determined as a function of emitter temperature, collector temperature, cesium pressure, and current. For all the data obtained, the emitter temperature profile was measured by thermocouples. From the calorimeter measurements, correlations were found for the prediction of emitter electron cooling DELTA Q/sub E/ and collector electron heating DELTA Q/sub C/: DELTA Q/sub E/ = I (2.6 + V), and DELTA …

A digitizer and data handling system that measures the locations of images on transparent film by automatically scanning an area with a mechanically generated flying spot of light is described. The location measurements are directiy transmitted for processing to a digital computer, which also controls the digitizer operations. A 4 in. x 5 in. negative can be scanned by a roster with a pitch of 50 mu in about 3 min. (D.C.W.)

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Thesis submitted to University of Tennessee, Knoxville. A double time- of-flight apparatus constructed for measurements on fission fragments is described, and the theory and procedures for the measurements are outlined. The accuracy of the technique, limitations of the apparatus, and physical factors affecting the measurements are analyzed. 44 references. (D.C.W.)

This note derives some relationships between the various parameters describing the nuclear pulse rocket, and gives numerical examples of performance attainable under the assumption of a fixed chamber temperature.

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About 298,000 OIIIN aluminum components were received from Harvey for evaluation after major steps were take in the vendor`s plant to upgrade product quality. This material met HAPO specifications and was comparable to Alcoa control components. Finished fuel elements (non-bumper and bumper) canned in the test and control components are tabulated by uranium core type and canning month. Non-destructive and destructive test data did not show any differences in clad fuel elements attributable to component quality. Irradiation status of non-bumper and bumper fuel elements clad in Harvey improved components as of Dec. 31, 1962, is tabulated, as is a summary of ruptures. It was recommended that Harvey Aluminum Co. be allowed to bit competitively on all future Al component orders except for the KVN and KVE component models.