During the spring 1952 atomic weapons tests a nationwide network of weather stations, supplemented by 16 foreign stations, collected samples of settled and airborne dust which were counted radiologically. The data are reported as bases for estimating possible health hazards.

This report provides details of a test to determine the feasibility of preventing corrosion of the 107- C retention basins by the installation of a small scale cathodic protection system.

It is the purpose of this document to record the significant steps in the removal of a ruptured slug from tube {number_sign}2562-H.

Many factors are responsible for the rapid growth of analytical chemistry during the past ten to fifteen years (This report was written in 1953). One of the most important of these factors is the greatly increased significance to present day chemistry of many elements that in the recent past were principally chemical curiosities. Since the Atomic Energy program is concerned with many such elements, it is of interest to discuss the cause for this concern and the resulting effect on the field of analytical chemistry. A number of pertinent analytical research problems at Hanford are cited as examples.

The demand for filtered water will be increased when I and E slugs are charged into the reactors. Some of the filter plants are near their ultimate capacity. One of the quickest ways of obtaining increased amounts of filtered water for production use is to restore to normal process service certain filters which are now isolated for exclusive drinking water use. These drinking water filters are isolated because the process water filters are being treated with Separans, a material which has not been approved for use in drinking water. A suitable approved substitute material was found and tested in the model filter at B Area. A full scale plant test was run at F Area for the purpose of confirming the results obtained in the model filter plant. The results of the full scale toot are presented in this report.

during the December 1953 extended outage the process water flow at C Reactor was increased and redistributed to allow reactor operation with a 69 tube enrichment ring in the third lattice unit and with the maximum protection afforded by the trip before boiling operational concept. The redistribution was accomplished by the installation of individual venturi flow meters on approximately 1800 process tubes. Flow and pressure requirements were met by the installation of larger diameter conventional Hanford orifices on about 200 tubes. During the outage, the original Panellit gages were replaced with improved Panellit gages equipped with long vane mercoid switches. The purpose of this memorandum is to review and report the results of the reorificing program and to compare them with predicted behavior.

Reactor gas costs have increased substantially each year since 1952 when the total cost was $108,000. In 1953, 1954, and 1955 the gross annual cost of reactor gas was $126,000, $348,000 and $606,000 respectively and are reported in Figure 1. These continued increases in reactor gas costs indicate the need for an analysis of gas usage and formulation of a program to reduce gas consumption. To provide basic information for such a program, a critical review has been made of the reaction gas system and gas consumption figures for the past four years.

This report records the basis underlying the decision already reached to recommend a change of process tube fittings at B, D, F, DR and H reactors, and also proposes for consideration a change in the devices for monitoring effluent water temperature.

Nuclear reactors which contain a significantly large volume operating at or near the same flux level are subject to oscillations of the maximum flux from one region of the reactor to another. To control these flux movements it is necessary to know the location of the flux ``peaks`` and ``valleys`` and the rate of change of the flux at these points. Existing monitoring instruments readily present only a two-dimensional picture of the flux distribution within the reactor; the front-to-rear distribution must be inferred from graphite temperatures or octant monitoring chambers which are not ideally suited for the job. The objective of this test vas to evaluate a paired-column arrangement for continuously monitoring the front-to-rear flux balance in one region of the reactor and to control any significant unbalance with the prototypic slug column displacement equipment.

During a routine beta-gamma hand and shoe count, an employee discovered that his shoes were contaminated. This document discusses the spread of particulate contamination at the Biophysics Laboratory, Building 329, 300 Area on July 6, 1954.

This report summarizes the design and development work completed since May, 1957; the current status of fuel element matching problems, and the plans for future modifications to improve machining techniques.

Areas covered in this report are as follows: nuclear safety in the Fuel Preparation Dept.; studies related to the present production reactors; studies related to future production reactors; studies related to separation plants; studies form the neutron cross section program; reactor development (gas cooled reactor program and test reactor operations); and biology and medicine.

Sometime was available for development and improvement for future designs before K pile design was authorized. One of the objectives of this development program va was to improve upon downcomer design. It as evident that the proper approach to the problem lay not in duplication because of inadequate facilities as a means of circumventing the resultant effects of failure, but rather in the adoption of a more logical engineering approach -- analyze the cause of failure, profit from the past operating experience and concentrate upon the removal of these inherent difficulties. Accordingly, a downcomer design embodying a superior method of operation was designed and tested. The design minimizes vibration by dissipation of energy through a series of orifice screens rather than impact loading of large parcels of water and turbulent friction. It greatly simplifies the maintenance problems by designing for essentially complete replacement of the downcomer by ordinary maintenance methods. It provides for very rigid construction of the inlet section and 30 parallel flow paths in the vertical portion and thus the problem of blocking the flow has been eliminated. A detailed analysis of the points is presented in this report.

This test as detailed in this report is one of three parts of the initial testing program to demonstrate enriched usage at HAPO. It proposes to irradiate two twelve-tube blocks of enriched uranium and lithium-aluminum slugs to obtain conversion ratios and preliminary information concerning slug stability.

Described herein are studies on pile control, shielding, process tube assembly, pile operating equipment, pile renovation, power recovery, pile piping and the 189-D test laboratory at Hanford.

This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two longitudinal planes at the male end. The distortion planes are at right angles which gives the transverse section a square a appearance. A comparison of the grain size from three positions along the warped element with a section cut from the unwarped element revealed a greater number of large grains in the zones of highest distortion. The maximum size grains, were in the order of 2.5 mm -- 3.8 mm vs normal .2 mm. Also prevalent in all sections examined vas a columnar type grain structure around the outside periphery. It is evident that the pre-irradiation heat treatment failed to refine the grain size sufficiently to prevent nonuniform growth of this element during irradiation. A corrosion pit was …

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This report describes an IBM 704 Computer program for the calculation of transient temperature distribution in axially symmetric solid or hollow bodies. It is the first part of Transient Thermal Stresses in Pressure Vessels. The present report mainly describes the use of the computer program and gives, for two problems, a comparison between computed and analytically known results. The analysis is reported briefly in this report.

As a part of the Productivity Increase Program, consideration should be given to further gains in 100 Area production levels which can be achieved by further increases in both light and heavy water flow rates. This memorandum presents a summary of the power level gains which should be achieved from the flow increases under consideration, a discussion of the costs and production losses which might apply, and a brief listing of some other considerations which might influence any decision to increase flow rates further.

Experiments were conducted to determine the relative flow characteristics of J-pigtail adapters supplied by Lampson Products Co., Seattle.

Recent experiments show that soil uptake of plutonium by cation exchange from Recuplex process waste is practically negligible. Additional experiments with synthetic cation exchangers also produced negative results. The plutonium occurs in the form of an anion nitrate complex, precluding the possibility of plutonium removal by cation exchange. As a result, a laboratory investigation was started to determine the effectiveness of synthetic anion exchange resins for removing plutonium from these wastes. The initial results of this investigation indicate that a fixed bed ion exchanger may be utilized to remove a large part of the plutonium from CAW waste. Laboratory work is continuing to define the optimum resin and operating conditions.

This monthly document details activities of the Hanford Operations Office during the month of March 1959. (FI)

It was recommended that the control rods in the septifoils of the reactor be reoriented in order to improve flux shaping; burnout was not mentioned. This memorandum re-examines the problem of orientation of the control rods considering not only flux shaping but also burnout.

This monthly document details activities of the Hanford Operations Office during the month of May 1959. (FI)