The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)

None

The lifetime for the decay of a {pi} meson into {mu} meson and neutral particle was first measured by Richardson and later by Martinelli and Panofsky. The method was the same in both cases: The fraction of {pi} mesons surviving various times of flight is measured by placing photographic detectors at various path lengths from the target. In the experiment reported here we observe the time lag between the two bursts of fluorescence due to mesons decaying in a scintillation crystal. The first burst is due to the stopping of the entering {pi} meson, the second to the {mu}-meson. As is shown in Fig. 1, a particle penetrating the first and into the second crystal starts the sweep (10{sup -8} sec/mm) of an oscilloscope. The pulses in the second crystal are delayed 0.5 x 10{sup -6} sec to allow the sweep to start and brighten and are then photographed. If the responsible particle is a {pi}{sup +} meson which stops in the crystal, it undergoes {pi}-{mu} decay and two pulses appear on the trace. The {mu}{sup +} meson has a range of only 2 mm in the crystal. If its decay electron is detected some time (.5-2.5 x 10{sup -6} …

In view of current work on the Columbia River by the Biology Division and Development Division of the Health Instrument Divisions and the contemplated studies of the US Public Health Service Group new at Hanford, it was suggested that the groups review their programs related to studies of the Columbia River. The work carried out by the Control Functions Section of the Health Instrument Division in this respect is reviewed in outline form. Some of the studies are jointly carried out by the Control Functions Section and the Methods Group of the Environmental Hazards Section. The principal purpose for monitoring the Columbia River is to evaluate any radiation hazards that might exist as the result of discharging radioactive effluent into the river from the Hanford pile areas. The miscellaneous special studies conducted so supplement the routine monitoring program are pointed at into the river to better understand the effects of this radioactive contamination on the environment of the river and/or any drinking water supplies using the Columbia river as a source of supply. 1 fig.

During the first 15 months of operation of the Redox process, it was clearly demonstrated that in the absence of any pre-solvent extraction treatment of the starting metal solution, ruthenium contributed from 75 to 95% of the remaining fission product activity in both the final uranium and plutonium streams, and that three solvent extraction cycles were able consistently to produce, at best, only marginal quality product. This precarious position was further endangered by a three-fold reduction in the gamma radioactivity specification for recovered uranium shipped from Hanford, and by increased power levels in the reactors, resulting in still higher fission product concentrations in Redox feed solutions. The purposes of this review are to summarize briefly: (1) the chemistry of Ru in the Redox process; (2) the permanganate head-end treatment and its associated problems in plant operation; and (3) alternate possibilities for the elimination or control of Ru, including those which might solve the permanganate process difficulties. It is also the purpose of this document to present a selected bibliography on the subject of ruthenium specifically for those points under discussion herein. 17 refs.

A knowledge of the mechanical and physical properties of uranium is important in understanding its pile behavior. The effects of irradiation on the properties of uranium will be dealt with in another chapter. However, it is important to know and understand the pre-irradiation properties of uranium prior to investigating the effects of irradiation. This chapter discusses the mechanical and physical properties of uranium.

This report covers the examination of nine process tubes, five tubes from B Pile and four from H Pile. Four of the tubes from B File were removed because they were leaking and the fifth was removed because it contained a stuck ruptured slug. Tube 2681-H was removed for graphite mining, tube 2852-H was removed under PT 313-105-14M ``In-Pile Evaluation of 63-S Aluminum Process Tubes,`` and two tubes were removed from channel 0961-H under PT 105-506-E, ``Recirculation of Pile Cooling Water.`` Visual inspection was made of the inside and outside surfaces of the tubes before and after cleaning with cold 10 per cent nitric acid. Samples varying from one to four inches in length were taken from each section and transferred to the 108-B Metallurgical Laboratory for close examination to determine depth of pitting, 72-S cladding thickness, and wall thickness. These determinations were made at specific points in each section on what appeared to be the area of severest attack. It is indicated on six of the tubes where the sample was taken on the circumference of the tube.

This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.

Recent successes with the use of metal ferrocynanides, particularly nickel ferrocyanide, for the removal of cesium from Uranium Recovery Process wastes prompted an investigation into the use of this carrier for the removal of cesium from wastes produced in the coating-removal and first-decontamination-cycle steps of the Bismuth Phosphate Process. Both in-line treatment of the wastes currently produced and treatment of supernatant liquids from wastes already stored in underground tanks were considered.

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this programs, it is estimated that 1650-2350 megawatts of total additional production will be achieved. The purpose of this document is to set forth the design for certain modifications and additions to Hanford reactors and their supporting facilities as required to obtain higher power levels and improve the safety of reactor operation.

The objective of this test is to authorize irradiation of pilot quantities of alloyed dingot uranium and to provide for monitoring of its performance. This test will authorize: (a) Charging of up to 50 tons of alloyed dingot fuel elements in two groups of 25 tons each, including 12 monitor charges which will accompany the first group, into D Reactor as a pilot loading. Although purer and ore dense than standard ingot uranium, the dingot uranium produced in the past by MCW has demonstrated poorer dimensional stability during irradiation. The instability has been manifest as warp, nearly double that of ingot which was irradiated in the same charge and by surface bumping up to 5 mils in height. Both the bumping and the warp are normally associated with large grain size, non-uniform orientation and/or residual stresses. To improve the stability,, primarily by grain size reduction, additions in the range of 150 ppm iron and 100 ppm silicon are being made to the green salt prior to reduction. The hydrogen content of the metal has been reduced by pre-heating the green salt at high temperature prior to triggering the metal reduction. Further refinements to the process include heat treatment in chloride …

A meeting of the Thorium Working Committee was held at FMPC on September 20, 1955. The current status of the thorium production program was discussed and a limited development and evaluation program was outlined which it is felt will (1) clear up some of the more important question marks in thorium metal quality and (2) develop a more satisfactory method for processing solid metal scrap. The basic parts of this immediate program are (1) SRL would evaluate ingot sections of as-cast double arc-melted virgin metal in order to classify typical ingot defects and determine their frequency of occurrence; (2) Du Pont would request for evaluation purposes ingot sections from typical recycle ingots which incorporated vacuum-induction melting for the consolidation of recycle metal in the form of consumable electrodes for arc-melting; (3) after completion of item (2), du Pont would then request approximately 200 slugs, made from suitably processed recycle metal, which would be used for canning and steam autoclave tests. This program should lead to definite specifications (and/or classifications) for ingots to be stockpiled for future AEC use.

The objective of this production test authorization is to permit the irradiation of sixteen, 0.394 inch diameter, metallic uranium spheres at temperatures between 300C and 800C in the 3674 ank 3865 KW front-to-rear test tubes. Eight spheres will be of natural uranium and eight of enriched (3% U-235) uranium. Temperature controlled and temperature monitored test capsules containing either four natural or three percent enriched uranium spheres will be irradiated. Pre- and post -irradiation examinations will be performed to determine the extent of swelling. The temperature of the spheres will be controlled at the same constant level during reactor operation and during shutdowns. Capsule exposures will vary from one to 24 months. This production test authorization will permit the irradiation of two capsules each containing four natural uranium spheres and two capsules each containing four three percent enriched uranium spheres.

This report discusses a meeting held on November 8, 1956 at BMI, Columbus, Ohio, for the following purposes: To determine the best method of electroplating uranium cores for extrusion cladding; to determine if there were any shortcomings in the SRL method of plating which could be the cause of the poor bonding experienced with internally extrusion-clad tubes; and to make what corrections and revisions were necessary in SRL plating procedure to assure the optimum quality of nickel electroplate on the basis of present information.

Brittle bonds and the factors controlling their formation have been of substantial concern in the production of dip canned fuel elements. Detection of brittle bonds has been by the chisel test and by metallographic examinations. At best, these are qualitative tests and do not establish the degree of brittleness. For this reason bond tensile strength analysis has been suggested. Tests have been run to determine if a change in canning variables could be detected by a change in bond strength.

This report is a summary of projects worked on in support of the production reactors at Hanford. The projects include criticality studies, from tasks associated with fuel element reprocessing to shipments of slightly enriched uranium. They include studies of neutron cross sections for different reactions and neutron flux measurements in different reactor locations, as well as design studies for future reactor projects.

None

An evaluation was made of the use of NaK as the primary coolant for the SNAP-2 system. Pumping-power limitations based on the mercury Rankine cycle are analyzed. Problems pertinent to any design-specification modifications are reviewed.

None

A new slug for U-233 production consisting of a solid thorium core externally jacketed by a thin Oralloy foil is described. Advantages of this system are pointed out. The bulk of this report concerns itself with the long-term changes of reactor parameters as the foil slug is irradiated at constant specific power (kilowatts per foot). Isotope yield curves are also presented.

The angular relationships of warp to rib marks and warp to hot spots were measured for a large number of fuel elements. The data was analyzed and found to provide information regarding the formation of warp and hot spots.

The masonite in the old pile shields is deteriorating because of the temperature conditions to which it is subjected. One method of mitigating this deterioration is to reduce neutron leakage to the shields by utilizing the fringe tubes for target material. One possible target material is depleted uranium, i.e., uranium from which the bulk of the isotope 235 has been removed. The purpose of this test supplement has been to irradiate a fringe depleted pattern to establish the enrichment loading of E metal necessary to maintain reactor production, to determine the depression in shield temperature which could be obtained by such a loading, and to establish the operational economics of this method of production. The latter of these goals is to be the subject of a later report. With full length depleted uranium charges in the outermost fringe process tubes the heat generation rate in the adjacent shields is reduced to approximately 75 per cent of the value for a natural uranium loading under comparable reactor conditions. The reactivity compensation can be achieved by the use of one and one-half full length E columns for each depleted column where the E charges are placed in the second an third tube …

Assistance has been requested by Financial Operation to determine the percent of firm and interruptible power used in each area for cost distribution purposes. Also, Power Operations have suggested that the power cost distribution be reviewed. In consideration of these requests, and with the use of improved demand instrumentation within the 151-B, D, and F substations, a proposal for equitable IPD electrical power cost distribution between areas is presented for acceptance or comment by Area Management.

On the basis of numerous rough calculations it has generally been assumed that if the water flow to a tube were to stops while pile operation continued. The tube central temperature would increase in a matter of seconds to dangerously high values. In several seconds the water around the central slugs would flash to steam, shortly thereafter the aluminum cans would melt and this would give good contact between the slug and the tube which would quickly melt. The bare uranium would react with the steam and possibly the pile gas atmosphere. Radioactive Xenon and fission products would be spread through the gas system, and the molten aluminum and uranium would fill up all of the cracks in the graphite and the tube would be impossible to discharge by all normal methods after the pile is shut down. If the pile were operated with this tube blocked off there would still be the problem of exceedingly high graphite temperatures around it, and the spread of contamination in the gas system. Because these problems are expected with an undetected water failure in a pile, where the operation is maintained, a program is underway to ensure proper and sufficient tube instrumentation to …