This report discusses work at the Hanford engineering Works` 100 and 200 areas for August 11th through August 17th, 1944. Topics discussed include canning, slug recovery, testing and miscellaneous items. (JL)

An estimated minimum critical mass for each of the process vessels in the 231 Building has been calculated on the basis of critical mass data given in the P-11 Project Document HW-24514. The calculations are made assuming the plutonium to be a homogeneous mixture of precipitate and water with some slight neutron poisoning due to other elements. The precipitate is further assumed to have partially settled making an effectively infinite water reflector above the plutonium and hence reducing the critical mass.

Tube 1794-C was removed from the pile as a leaker on July 15, 1954. The tube had been in-pile since startup and had contained a charge of 32 ``C`` metal slugs just prior to discharge. The tube was slit and examined at the 105-DR underwater viewing facility by Pile Coolant Studies tube examination personnel. A report is made of the examination of tube 1794-C which revealed areas of severe pitting damage. This damage was apparently caused by cocked slugs abrading the tube. The attack was great enough to cause perforation of the tube at about 27 feet from the rear Van Stone flange. Examination of the slugs showed that a considerable number had been cocked. Evidence of severe tube scarring and rib grooves was found on the slugs. Strikingly similar examples of pitting and grooving were observed on flow laboratory minitubes and slugs exposed in high velocity water. It is concluded that the damage observed both in- and ex- pile was caused by the chattering of misaligned low density slugs in a high velocity stream. If the number of in-pile occurrences of this attack becomes excessive it is recommended that the water flow rate in tubes containing ``C`` metal slugs …

Portions of the Hanford Reservation in 1954 had significant particulate contamination from the Redox process. This paper is about the methods used to decontaminate the Reservation. The two methods are decontamination and access control. A general description of the ideas and benefits of each method is given. (MB)

This report describes the direct essential material requirements for processing a standard run through the precipitation separations process in effect on August 1, 1954. Flow sheet conditions are based on a starting maximum batch size of 300 grams of product at a uranium irradiation level of 215 MWD/ton. The essential material requirements are those used to process with 2.5 grams of Bismuth per liter in Extraction, First Decontamination Cycle volumes at 56% of the September 1, 1946 standard, and Second Decontamination Cycle through the Lanthanum Fluoride Product Precipitation volumes at 49% of this standard.

The objective of this test is to establish that scavenging of first-cycle wastes in the Bismuth Phosphate Plant will give a supernatant liquor, after the precipitate settles, that may be routinely cribbed. This test will also perform the functions: establish an effective scavenging procedure, shakedown the pH monitor, and train operational personnel. This document discusses test procedures and results.

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For greater understanding of possible explosion hazards, data are needed of the volume of H/ evolved in the Ca and Mg reactions with nitric acid. Nearly five liters of H/sub 2/ per mole of Ca are produced when 16M nitric acid reacts with Ca metal. The hydrogen evolved slowly increases with decreasing nitric acid to below 4M nitric acid, when a rapid increase occurs. The Mg--nitric acid reaction produces only one liter of H/sub 2/ per mole of Mg with 2M nitric acid, and the volume of H/sub 2/ decreases with increasing nitric acid concentration. (L.T.W.)

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This summarizes the work done to date on the development of an epoxy resin bonded explosive (HMX). The original target values have been satisfied and further investigations will be on a semi-pilot plant scale.

This report summarizes the work done to date on the development of an epoxy resin bonded explosive (HMX). The original target values have been satisfied and further investigations will be on a semi-pilot plant scale. The following characteristics have been determined on laboratory specimens. Compressive strength, 11-12,000 psi; sensitivity (50 % height) 31 cm; density, 1.81 gm/cc; vacuum stability (cc gas/gm/24 hrs at 100{degrees}C), .42 cc/gm.

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Some of the factors controlling tissue growth in animals and cell proliferation in unicellular organisms are reviewed. Radiation damage in diploid yeast cells manifests itself sometimes in delayed lethal effect and decreased cell division rate over several generations in the progeny of the irradiated cell. Recovery of the progeny of irradiated yeast cells from phenotypic expression of radiation damage can be delayed over many generations and is similar, in time rate of onset to the onset of radiation induced animal tumors. A parallel suggests itself between the mechanism of somatic-radiation carcinogenesis and delayed recovery of unicellular organisms from radiation effect. (auth)

This report describes the operation of the fuels preparation department for the month of July 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

A maximum leak rate of 0.08% was measured for a piston ring seal assembly which was evaluated for use as the Hallain Power Reactor process tube- grid plate seal. A maximum leak rate of 0.14% was observed after subjection to 10,000 cycles (560 hr) in 625 deg F Na. The maximum leak rate was 0.07% after 25 cycle exposure in 1000' Na. Vertical scoring of both the rings and bore tube was observed. Sodium was observed to remain behind the rings after washing. (C.J.G.)

A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)

The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)

An evaluation of 300- and 100-Mwe power plants was conducted using ground rules prescribed by the USAEC for this study. Costs corresponding to two average discharged fuel burnups are: 8.6 mills/kwh (8500 Mwd/ metric ton) and 8.8 mills/kwh (7500 Mwd/metric ton) for the 300-Mw plant. Costs for the 100 Mw plant are 14.7 mills/kwh for an average discharged fuel burnup of 6010 Mwd/metric ton. Estimates of future potential indicate that the 300 Mw/sub 3/ (8500 Mwd/metric ton) plant could produce power for 7.3 mills/kwh in a second generation, full scale plant of the same type. A further reduction to 6.4 mills/kwh should be possible as the result of the recommended ten-year development program. The current development program is adequate for providing the data needed to design and construct a prototype reactor. However, there is no natural U-fueled prototype and no prototype of the chosen reference design scheduled in the U.S. Current technology is sufficiently developed to initiate the design and construction of a pressure tube, boiling D/sub 2/Ocooled, natural UO/sub 2/- fueled reactor prototype plant in the immediate future. This plant would demonstrate the main features of a full scale plant and, in addition. would provide design data which could …

Structural evaluations were made of the 15% cold-worked Zircaloy fuel- element containers proposed for the NS Savannah reactor. These evaluations, which are consistent with the Navy Code, permitted the sizing of components so that under conservative loading conditions both stress and deflection limitations would be met. The necessary design modifications were specified for the fuel- element container assembly. (auth)

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A small, self-powered, acoustic transponder was designed, fabriated, and tested to demonstrate the feasibility of producing a minimum-szie transponder package capable of operating at slant ranges of several miles in a deep-water environment.