Production of tetrafluoride for the month of April was 49,400. New equipment installed late in March operated smoothly and the production was slightly over the rated capacity of the plant. Nickel ends were welded on to the steel reactor tubes to prevent corrosion at the cover joint and possible contamination of the product with iron. The nickel ends will also save considerable repair work on the tube ends. The magnesium trays for some of the reactors are beginning to crack at the sides from frequent straightening. The trays are bent out of shape by the expansion of the product and are reshaped by hammering over a die. Some of the cracks have been repaired by welding but this is not very satisfactory because the welded trays are harder to straighten and often crack again.

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The following is a report of a trip to the Simonds Saw & Steel Company, Lockport, New York, on May 3, 1949. The purpose of the visit was to observe the various operations involved in the rolling of uranium rods at this plant and health problems associated with the rolling operations.

This report details events of importance reported by the Hanford Operations Office for the week ending May 11, 1949.

A common and useful assumption is that the front-to-rear power distribution is a shortened cosine curve. This fact led to the calculation of slug factors'' for the longer charges to be used at K-Pile. It is hoped that the publication of these numbers will save time and prevent duplication of effort by those concerned in any way with slug power, surface temperatures, reactivity effects, etc. For the sake of completeness, slug factors for the older piles are included. Another useful ideal is that tube power distributions can be approximated by the assumption of a cylindrical pile and a cosine distribution of power outside of a central flattened region. This led to another double set of numbers since the values for the 2004 tube piles were again included for completeness. 2 figs., 6 tabs.

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In a preceding lecture all the components necessary to secure a controlled nuclear chain reaction were discussed. The business at Hanford is to use these components in the most efficient manner possible to manufacture the desired products of irradiation - the primary product being Pu. In this lecture of the variables of such operation are considered.

This test consisted of a series of helium purges of the pile gas atmosphere to bring the helium content up to about 70 to 80% helium followed by a series of CO{sub 2} purges to restore the pile atmosphere to its initial composition. The purges where spaced roughly four hours apart to enable the reactor to reach a steady temperature before purge was undertaken. The test results are presented in this report.

The purpose of this report is to summarize all actual and potential power level limits under which the K Reactors may be forced to operate during the next year. In addition, a summary of the methods being followed to eliminate each is to be discussed along with a graphical presentation of the relationship of the various limits. For the purpose of this report, it was assumed that all power levels will be attainable from a physics aspect since these problems are discussed elsewhere. It is not the intent of this report to recommend that these power levels be attained but only to indicate what production levels are possible through operation on any one limit. Seven outlet temperature limits govern operation at the K Reactors. They are: TBI Limit; Crosstie Limit; Rear Header Saturation Limit; Bulk Outlet Temperature Limit; Tube Corrosion Limit; Temperature Monitor Limit; and Rupture Control Point. Operation during the summer months of 1957 will require cuts in power in order to remain within these limits unless modes of circumventing a few are found. The limits are shown graphically in the appendix at the various flow rates probable. From these curves it is evident that the Low Trip TBI …

This report addresses the AEC symposium on particle-fluid mechanics

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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, materials, and processing are presented. Also included are drawings and the process flow diagram. (M.C.G.)

Specifications were prepared for the control rod absorber sections for Core Il of Army Reactor PM-2A. The neutron absorber section was composed of composite plates welded into the form of a rectangular parallelepiped. The composite plates were made of compacts of europium oxide in a stainless steel matrix clad with stainless steel by hot-roll bonding. Specifications covering materials and processes are included in the repont along with fabrication qualification tests. (M.C.G.)

Specifications were prepared for stationary fuel elements for PM-2A Core Il. Stainless steel-base fuel compcnents of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully used in the Army Reactor (SM-1). The component consisted of eighteen composite fuel plates joined by brazing, and was designed for radioactive service in pressurized water. Fabrication qualification tests and specifications covering loading, materials, and processing are presented. Also included are applicable drawings and the process flow diagram. (M.C.G.)

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. (auth)

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.)

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 included. (auth)

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 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.

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This monthly document provide source and special nuclear material composition of ending inventory reports for the month of April 1966.

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