Tests were conducted to determine the direction and magnitude of any short- or long-term drift in core thermocouples, primary loop and pressurizer resistance thermometers, and resistance thermometers located in the secondary side of the boilers for Seed 2 at 2303 EFPH. It was found that drift in the core thermocouples is definite but random. Other findings are discussed and calibration data are presented graphically. (J.R.D.)

An analysis of the EGCR core structure was made to determine the lateral deflections (bowing) of the graphite columns resulting from shrinkage caused by fast-neutron irradiation, the life expectancy of each column due to restraints imposed on the bowing, and the reaction forces induced in the supporting structures. Based on currently avallable data for EGCR type graphite shrinkage and assuming experimental loop operation, a maximum bowing potential of 3.61 in. was calculated for an interior column. It was found that strains equivalent to the rupture strains observed from tensile tests could be expected after 4 to 6 years of full-power operation. Over half of the columns will reach these strains before the 20-yr reactor design life is reached. (auth)

Corrosion studies were conducted on stainless steel types 347 and Carpenter-20, Monel, titanium 55A, and tsntalum in decontamination solutions. These solutions are: 10% nitric acid, 10% citric acid, 10% sodium hydroxide--2.5% tartaric acid, 10% oxalic acid, 0.003M periodic acid in 0.05M nitric acid, 3% sodium fluoride --20% nitric acid, Turco 4501 and Turco 4502, and 0.25M phosphoric acid. Boron stainless steel type 304L was studied in 10% sodium hydroxide--2.5% tartaric acid, 10 and 60% nitric acids, Turco 4501 and Turco 4502. The two austenitic stainless steels were found to be acceptable construction materials for handling each of the decontamination solutions except 3% sodium fluoride--20% nitric acid. Special limitations are defined for Monel, titanium 55A, and tantalum when exposed to decontamination reagents. (auth)

The effect of extracted zirconium and nitric acid upon the chemical stability of tributyl phosphate was investigated using gas-liquid chromatography. Tributyl phosphate was degraded approximately 1000 times faster by the tributyl phosphate-zirconium reaction than by the tributyl phosphatenitric acid reaction. Normal butyl nitrate was the major volatile product for both systems studied; with extracted zirconium a solid complex corresponding to the formula Zr(NO/sub 3/ )/sub 2/(DBP)/sub 2/ was also obtained. (auth)

This document details activities of the irradiation processing department during the month of March, 1961. 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; Financial Operation; and NPR project.

This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1960. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1960.

The present Quarterly Report is the continuation of a series issued by the new Fuels Development Operation. Reports in this series combine portions of the quarterly reports by the former Metallurgy Research and Fuel Technology Sub-Sections. Work reported includes research conducted by the Physical Metallurgy Operation, and research and development conducted by Fuel Design, Fuels Fabrication Development and Ceramic Fuels Development Operations.