The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)

The performance, reliability, stability, and reactivity lifetime variations of the Shippingport PWR are determined under normal steady state conditions. These characteristics are studied over a period of 758 EFPH, at a power level of about 60 Mw(e). Flux-tilt corrections and plant operations during this time are described. (T.F.H.)

It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.

Significant production gains could be made by improving metal rupture performance. A means of achieving this is by depeaking the axial flux distribution, thus reducing the maximum specific power for a given tube-power. The flux traverse program has provided some knowledge of front-to-rear flux, and was instrumental in prompting a change in the equilibrium HCR pattern during February, 1958. A ``before and after`` comparison of in-pile flux conditions is presented, and suggestions for further improvement are given.

This is the monthly report for the Hanford Laboratories Operation, February, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection operation, and laboratories auxiliaries operation area discussed.

Trends in reactor operation and maintenance have created the need for a rear face Hanford reactor manipulator which can routinely perform certain maintenance and operational functions, and which under high radiation exposure conditions can permit ruptured slug removal or other emergency type operations tb be conducted with little or no personnel radiation exposure. Because of the need for several tools, it was decided that the most desirable approach to a satisfactory manipulator program would be to provide a multi-tool manipulator which could do several distinct tasks. Of these tasks removing the rear face nozzle caps to facilitate removal of ruptured slugs and performance of ruptured slug removal operation were the most profitable routine functions which could be accomplished by a manipulator. The conventional mechanical arm was considered for use in non-routine situations such as recovery of slugs lodged in rear face piping or other disaster type situations which on occasions do happen. To insure the quickest return on the economic benefits of the program, the cap remover development was conducted as a separate study since it is more definitive then,the remainder of the manipulator program. A second phase involving the application of the mechanical arm and development of specialized tools …

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The objectives of the test described in this report are to obtain current knowledge of the flow characteristics of the B and C Reactor flow systems under various transient conditions that have a reasonable probability of occurrence. These tests will be used to revaluate the B and C Reactor bulk temperature limits, the Ball 3X low pressure trip settings, and quantitative adequacy of emergency flow from the combined high tanks - export system.

The objective of this test is to determine the quality and erosion resistance of cape and cans produced from cast X-8001 alloy blanks through fabrication and irradiation of limited quantities in accordance with the testing procedure herein defined. Components which were fabricated from X-8001 alloy cast blanks have been subjected to rigorous out-of-reactor tests and have indicated equivalence or possible superiority to standard X-8001 alloy components. It is, therefore, proposed that; (1) six enriched charges of (0.94% U235) test material alternated with standard control material be irradiated; two to 500 MWD/T, and four to 800 MWD/T goal exposures in an old reactor, to compare corrosion resistance and (2) up to 240 charges of test enriched fuel elements be irradiated to normal variable goal exposure for enriched I&E in the same reactor, to further evaluate the performance of the components fabricated from cast blanks.

The in-line monitoring instruments installed in the Redox plant in the late 1950s consisted of six gamma monitors, a single channel gamma spectrometer, an alpha monitor, and a neutron counter. A gamma monitor on the steam condensate outlet line and a uranium monitor on the 2DFS stream were to be added at a later date. The first section of this information manual describes the in-line gamma monitors and gives operating instructions for them. The second section covers the alpha monitor, and the third section the neutron counter. Sections on the uranium monitor and the steam header gamma monitor were to be added at a later date.

A Task Force was established in the Irradiation Processing Department to examine the K-Reactor Water Plant to (1) review the operating and maintenance experience with the water plant as improved since startup, (2) identify major plant additions which could further improve reliability, and (3) estimate the costs of any such additions. The K-Water Plant basically consists of the electrically driven primary cooling system with power supplied by the BPA system, electrically driven secondary or backup cooling system powered by a steam driven emergency generator pair, and a ``last ditch`` system consisting of hydraulic cross-ties between the two K-Water Plants. This report summarizes information developed in the course of the Task Force deliberations.

During the past several years higher pile power levels, variations in the uranium goal exposure, changes in reactor loadings, and resulting changes in operating practices have steadily increased reactivity transients following the reacotr shutdowns and start-ups. Consequently, since conditions influencing activity transient predictions have becomeincreasingly more varied, it has become more difficult to maintain prediction accuracy Trends related to operating practices, reactivity variables, and critical predictions have been presented previously for the years 1950 thorugh 1957. It is the purpose of this report to include the data for the year 1958. In addition to presenting the data for reference purposes this document discusses the trends in operting pratices reactivity variable evaluations, and the accuracy of reactivity predictions during the past five years. Bar graphs show the yearly averages of selected data obtained from the shutdown data sheets, montly reports, and routinereactivity balance reports. In addition to these averages a table presents maximum and minimum values wherever they are applicable.

This document details activities of the Fuels Preparation Department during the month of February 1959. (FI)

This document details activities of the irradiation processing department during the month of February 1959. 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.

The SNAP Experimental Reactor (SER) is a small power reactor that is to be built and operated in the original SNAP-II critical facility. The reactor is described, and the hazards previously evaluated for the SNAP II critical faciity are reviewed.

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Progress made in the field of spectrophotometry of molten fluoride salts is summarized. The high-temperature cell assembly designed and fabricated for use in this work is described, as well as the various types of sample containers used. Spectra of nickel fluoride, cobalt fluoride, chromic fluoride, and uranium tetrafluoride in LiF--NaF-KF (46.5-11.5--42 mole%) are presented. (auth)

Data are presented from a study of the effects of indoleacetic acid and kinetin on the growth of Amoeba proteus, Escherichia coli, and two species of yeast. Data are tabulated and reaction mechanisms are discussed. 95 references. (C.H.)

Data are summarized from a series of recently published papers which indicate that the tissue iron enzymes as well as the blood hemoglobin level play a role in the iron-deficiency state. Results from a study of the derivation, roles and fate of the antibody-forming cell in the rat indicate that antibody- forming cells in lymph nodes may be released to circulate in the efferent lymph and peripheral blood. Evidence indicates that the circulating cells may still contain formed antibody. Because of thcir form these circulating elements are designated lymphocytes. Strong evidence also implicates the plasma cell in the immune phenomenon. It appears that thc circulating blood contains two small round cells, one produced in the germinal centers of the spleen and other lymphatic tissue and having no known relationship to antibody production, while the other is apparently produced in the splenic red pulp, contains antibody, and is related intimately to antibody synthesis. In terms of site of production and function the two cells appear unrelated. Papers included which have been accepted for publication cover the effect of concurrent feeding of Tween 80 on the carcinogenicity of orally-administered 3-methylcholanthrene, data on the long- term survival of irrailiated mice treated with homologous …

Information related to the performance and operation of the Idaho Chemical Processing Plant is presented. The information is presented as answers to questions posed for Eurochemic assistance program. (J.R.D.)

Inconel can be used for thermal neutron flux measurements by means of its cobalt impurity or its chromium constituent where conventional monitors are unsuitable. The use of cobalt should also be applicable to other nickel alloys. Discriminatory counting is required. (auth)

This compilation contains 202 abstracts of reports and documents on subjects related to maritime reactor safety; the abstracts are indexed in thc AEC Abstracts of Classified Reports'' (ACR). These ACR references were listed as unclassified or declassified in TID-4021, TID-40.35, and TID-4035, Supplement 1. The abstracts were selected as a part of the preparation of the classified bibliography (ALI-50, printed August 30, 1958) on this same subject. (See also SO-6200, Septcmber 15, 1957, unclassified.) The abstracts are grouped according to the category of information they present; within each category, the most recent abstracts are given first. Subject, author, and report number indices are provided. A report number code key is not included. The report numbers used by the AEC Technical Information Service can be found in TID-85 (1st Rev.). The abstracts are those indexed through ACR Vol. 13 (1957). Because of the lag in abstracting, reports issued in late 1957 are not likely to be included. (auth)

The casting procedures, mechanical working characteristics, composite fuel plate fabrication, and fuel element assembly methods for a nominal 48 wt.% U- 3 wt.% Si -AP alloy are examined. It was found that localized clad thinning, resulting from dogboning'' of the fuel alloy, is essentially eliminated in composite Plates when this alloy is used in combination with 5154 Al frames and 1100 Al covers. However, fuel component dimensions are difficult to maintain within commonly accepted tolersnces in the brazing prccess because of the marked differences in the thermal expansion of the fuel alloy and the containment materials. The mechanical properties, irradiation studies, corrosfon testing, pneumatic pressure testing, and chemical reprocessing of the Si-modified alloy are also discussed. (auth)

Comments by ICPP personnel on questions posed by Eurochemic Company are presented. Included is information on a fumeless dissolution system, recycle and rework system, liquid waste storage, criticality. in-line instrumentation, and a report listing Idaho Operations Area costs. (J.R.D.)