It was found from graphite irradiations that the changes can be described by a growth component and a contraction component, and that the contraction is a linear function of exposure, while the growth is a function of both exposure and temperature which saturated at high exposures, say 3000 MWD/a ton. A graph is included. Contraction rate is determined for KW, KE, and H piles.

The effects of ``water mixing`` pieces on the axial flux distributions and reactivities of the K Reactors are discussed in this report. Two mixing piece configurations in the K piles are compared to provide a basis for determining the optimum configuration with respect to rupture control, reactivity cost and temperature cycling effects.

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

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

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

Two Zircaloy-2 jacketed seven-rod cluster elements will be irradiated in the 3674 KE front-to-rear test hole to an exposure of 1000 MWD/T and two elements will be irradiated in the 3674 KW front-to-rear test hole to an exposure of 2000 MWD/T. After irradiation, the elements will be sent to the ETR where they will be ruptured during reactor operation to determine the failure characteristics of co-extruded Zircaloy-2 jacketed cluster elements.

This report discusses the events from a chemical standpoint following a total loss of coolant disaster will not be altered in the melting reactor by the introduction of N metal. The interdiffusion of uranium and aluminum will be the dominating reaction, causing the blockage and tying up of the lithium in UAl{sub 3} which does not melt until after the uranium does. Pressure from the swelling UAl{sub 3} will extrude uranium-aluminum and lithium into graphite weep holes and block interfaces. The migration of lithium by vaporization will not became appreciable until well over 2000{degrees}C, well beyond the time when uranium and UAl{sub 3} have melted. The eventual result will be a diffuse distribution of uranium, lithium, and aluminium in the lattice. The E-N pile has a larger excess over required control capacity than the uranium provided the large reactivity poison tied up in the lithium is not lost. Compared to the natural uranium pile, the gain of reactivity on loss of coolant is less and the net temperature coefficient in the dry pile remains negative to higher exposures. Furthermore, permanent pile poisoning during meltdown is accomplished via two mechanisms both lithium and uranium redistribution in the lattice produce large negative …

The objective of this supplement is to authorize a change in the panellit trip range from 25--75 psi to 5--95 psi. The test hole facility consists of two concentric aluminum tubes which extend from the front face to the rear face of the reactor. The ID of the inner tube is 2--7/8 inch. Water from one crossheader supplies the annulus, water from another crossheader supplies the inner tube. The three-foot-long, .570 inch OD fuel element is centered in a 40-inch long aluminum holder which has an ID of 1.380 inch and an OD of 2.800 inch. The panellit gage which monitors the flow to the inner tube fluctuates to such an extent during start-up that on two occasions the reactor was scrammed. During equilibrium operation the panellit gage reading remains stable. A possible explanation of this behavior is that during start-up aluminum spacers which are in the inner tube as part of the test charge chatter and cause variations in the water path through the tube. It is further surmised that at equilibrium operation the pressure drop across the column in the tube is sufficient to suppress the chattering. It is concluded that extending the trip range to 5--95 psi …

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Changes in pile operating parameters, such as fuel exposure, paver, and reactivity gain upon water loss affect the potential reactivity of the operating, pile and, therefore, the amount of enrichment required to operate under the desired conditions. Similarly a change in ECT (through enrichment location) changes the amount of enrichment.needed to maintain a constant reactivity. Many of the factors which influence the operating reactivity have quite different effects upon the reactivity of the dry pile with the ball 3X system inserted; therefore, changes in operating parameters may cause sizeable changes in requirements for supplementary control to maintain sub-criticality in the dry pile. It is the purpose of this document to summarize these trends in disaster control requirements for the K piles. The trends are presented as graphs of supplementary control requirements against a single varying parameter. All other parameters are held fixed as specified on each graph. The fuel element (central orifice zone) for all examples is the K-2 slug. In general, the slopes of these curves are only slightly dependent upon the specific values assigned the fixed parameters, although the magnitude of the control requirements may be quite dependent on these values. Unless otherwise noted any dependence of the …

Following-the K-pile start-ups in early 1955, a program of planned power raises was begun. The operating level had reached 1700--2000 MW by late 1955, and a severe operational control problem became apparent; the power distribution in the reactor was difficult to control and appeared inherently unstable. A study of available data led to the initiation of a production test so that a more detailed study of the phenomena could be made. This report describes the measures taken which led to an improvement in the operating characteristics of the K-piles; the current status and future outlook are also discussed in a general way.

This report for January 1959, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance: Financial operations; facilities engineering; research; and employee relations.

Dogs, pigs, rabbits, guinea pigs, and mice were exposed to nuclear detonations in two open underground partitioned shelters. The shelters were of similar construction, and each was exposed to separate detonations. Each inner chamber filled through its own orifice; thus four separate pressure environments were obtained. An aerodynamic mound was placed over the escape hatch of each structure to determine its effect on the pressure-curve shape inside the chamber. In one test a sieve plate bolted across the top of the mound was evaluated. Wind protective baffles of solid plate and of heavy wire screen were installed in the shelters to compare primary and tertiary blast effects on dogs. The shelters also contained static and dynamic pressure gages, radiation detectors, telemetering devices, and, in one test, air-temperature measuring instruments, dust-collecting trays, and eight pigs for the biological assessment of thermal effects. One dog was severely injured from tertiary blast effects associated with a maximal dynamic pressure (Q) of 10.5 psi, and one was undamaged with a maximal Q of 2 psi. Primary blast effects resulting from peak overpressures of 30.3, 25.5, 9.5, and 4.1 psi were minimal. The mortality was 19% of the mice exposed to a peak pressure of …

The reaction between formaldehyde and nitric acid, in which the acid is destroyed with the production of predominantly gaseous products, has been recognized as of great potential value in the processing of radioactive fuels, particularly during waste treatment. Laboratory studies of the reaction at Harwell and at Hanford have shown that a major fraction of the nitric acid can be readily removed from an acidic solution containing nitrates by the addition of formaldehyde. The process possesses the advantages of low chemical cost; recoverability of nitric acid; and, in the case of waste treatment, the production of a solution relatively low in inert salt concentration suitable for fission product recovery or ultimate disposal. The primary purpose of the study was to confirm and extend existing information on the formaldehyde reaction to the destruction of nitric acid in Purex type waste (1WW) through operation of pilot plant scale apparatus. Operational behavior, formaldehyde utilization efficiency, and safety considerations were particular subjects of study. In addition, destruction of nitric acid in a Darex-type dissolver solution was investigated.

A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers for Pu(III) is described. Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid reduced Pu(IV) to stable Pu(III) in nitric acid. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV). (J.R.D.)

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Several functions used in the calculation of x-ray crystallographic intensities are tabulated over large ranges. These tabulations include Lorentz- polarization factors as a function of Bragg angle, the Debye function as a function of THETA /T, and the Debye-Waller temperature factor as a function of B for selected sin theta / lambda values. (auth)

The equations and nomographs most frequently used intended calculating behavior of stack effluents are given and explained. (T. R. H.)

Nuclear fuel cost of 1.25 mills/kwh would make nuclear power competitive with conventional power in lowcost coal areas if capital and operating costs can be brought to within about 10 percent of those of coal-fired plants. Substantial decreases in fuel fabrication cost are anticipated by 1970: other costs in the fuel cycle are expccted to remain about the same as at present. Unit costs and irradiation levels that would be needed to give a fuel cost of 1.25 mills/kwh are believed to be attainable by 1970. (auth)

Foreign research and power reactors are tabulated. Nuclear power buildup goals are given for each nation on which information is available. (J.H.D.)

The energy distribution of ions and electrons in DCX are being studied by means of the Fokker-Planck approximation to the Boltzmann equation. An IBM- 704 code, called FOPP, was constructed to solve simultaneously the coupled Fokker-Planck equations for each of the two species of particles. This report discusses the difference scheme employed and derives the boundary conditions necessary in order that this difference scheme conserve energy and particles in the absence of sources and sinks. In particular, detailed discussion is given of problems arising from the use of two grid sizes, which proved advantageous on account of the great difference in the mass of ions and electrons. (auth)

A process has been developed for converting nitricacid-insoluble uranium in ore concentrates into soluble form. Ore concentrates are treated with a reducing agent such ss carbon monoxide or hydrogen at temperatures or 670 to 730 C. In the laboratory, retention times nsoluble uranium vary inversely with the concentration or the reducing agent. Laboratory studies leading to the development of the process are reported. (auth)

Progress on various theoretical studies are reported. DC model magnet studies to determine the optimum size and position of correcting holes drilled in the magnet yoke are described The major design criteria for the ring magnet are given. The current in the magnet of the 12.5 Bev proton synchrotron was calculated. The power supply characteristics and operating conditions are described. The side coil assembly phase of the ring magnet ooil program is described. The radiofrequency system consisting of accelerating cavity, rndiofrequency program, noise-measuring systems, power amplifier, and beam inanction electrodes is discussed Detailed studies were made of the BNL Linac design and such modifications were made as are required to meet the specific needs of the ANL injector system. Two methods of fabrication of the ring magnet vacuum chamber are discussed. A preliminary study and desige was made of several vacuum pumpimg systems for the ZGS accelerator. Investigations on the vacuum properties of epaxy plastics, evapor-ion pumps, water flow control, and foundations are reported. (For preceding period see ANL-5564.) (W.D.M.)