The program of the Pile Graphite Studies Unit for the past two years has been directed toward relaxed graphite specifications. The main emphasis in these studies has been on the feasibility of higher permissible maximum graphite temperatures and higher percentages of helium in the gas systems. The success of this program is evidenced by the potential pile power levels permitted by present process specifications. The present graphite Process Specifications will not permit heat generation associated with tube powers above 800 KW at, B{sub 9} D{sub 9} and F Piles. Therefore, further relaxation is necessary if tube powers of 1000--1200 KW anticipated after completion of the water plant expansion program are to be realized. In extending the present program to permit these anticipated tube powers, production tests authorizing full pile tests for raising permissible maximum graphite temperatures and increasing the percentage of helium are necessary. A production test authorizing the operation of D Pile at sufficient constant power level to attain graphite temperatures of 460--500 C with 60{plus_minus}5 percent helium has been agreed upon and is now circulating for final approval. A production test has been prepared to evaluate graphite burnout, rates at maximum temperature of 600 C with localized regions …

This document discusses high radiation levels which are being encountered in the reactor discharge areas during outages. Rear face dosage rates in B, D, F, DR and H Reactors now average 100 mr per hour. These high radiation rates seriously jeopardize desirable projects which require extensive work on the rear face of these reactors. Evidence has been obtained which indicates that a large source of the radiation is on the interior of the rear face piping and can be removed by chemical solutions. Reference one presents data which indicates that up to 85 per cent of the gamma activity is caused by the contaminated film deposited inside the rear face piping. Reference two discusses the results of chromic acid removal of process tube corrosion products. Reference three more fully describes the possible advantages of purging a reactor with chromic acid and concludes a chromic acid purge should remove the film without adverse effects on reactor structural materials or process tube loadings.

The object of the production test described in this report is to obtain full pile high temperature graphite burn-out data. In addition, the test will supply valuable data on the postulated influence of neutron temperature on plutonium purity.

The attached unclassified article was prepared for publication in Civil Engineering. It describes construction techniques and equipment used in processing, prepacking, and grouting heavy aggregates used in the construction of the K-reactors.

This report brings together certain temperature information of the Columbia River which is related to the Hanford plant of the United States Atomic Energy Commission. The temperature of the Columbia River is important for a number of reasons including the possible effect on aquatic life especially the habitat for salmon and the supply of cooling water for the Hanford reactors. Since the heated cooling waters from these atomic reactors are returned to the Columbia River without substantial cooling, the re suiting river water temperature increase is monitored. Climatic conditions influence greatly the temperature and flow of the river. Of these, the solar heating effects are very important. In this review the flow and temperature of both the Columbia and Snake Rivers are considered.

This document provides details of the radiation monitoring efforts of the Reactor Section during the month of December 1954.

This monthly document provides activities of the Radiation Monitoring Group of the Reactor Section during the month of December 1954.

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This document details radiation monitoring activities of the Reactor Section during the month of March 1955.