Human iron metabolism has been extensively studied in the past twenty-five years with the radioisotopes iron⁵⁵ and iron⁵⁹. Before the availability of the whole body counter, however, iron absorption studies were performed by the indirect methods of fecal assay of unabsorbed radioiron, and estimation of red cell incorporation of absorbed tracer. The few long-term excretion studies performed required numerous assumptions, since human iron excretion was less well understood. Whole body counting provides a simple and accurate method of measuring the total body retention of administrative tracer iron⁵⁹, thus making absorption and subsequent excretion determinations possible with a single radioiron study. The energetic gamma emissions of iron⁵⁹ permit ready external detection with small quantities of isotope, Normal radioiron distribution is uniform throughout the circulating red cell mass and thus minimize geometry influences on the counting efficiency, 0nly the 45.1 day half-life of iron⁵⁹ limits long term iron turnover studies. Measurements of iron⁵⁹ absorption and long-term body turnover have been under way at Brookhaven National Laboratory for over two years. The present paper outlines some of the results of these studies, and discusses some implications of the method.

Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.

This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.

Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.

"Acoustic energy generated by mechanical or electrical signals and its effect on pool boiling of isopropanol were studied. Daring the course of the investigation, a method was devised to determine the amount of heat-transfer surface wetted by the boiling isopropanol. Plots of heat flux versus temperature difference for each frequency showed that the acoustic energy did not significantly affect the heat flux at burnout, but slightly increased the critical temperature difference. No general effect of frequency variation was found even at the frequencies of the "boiling songs" of isopropanol. The over- all effect of the acoustic energy was to disturb the vapor tending te coat the heat transfer surface. This was most evident from the absence of film boiling even at temperature differences far above the critical temperature difference. The application of alternating current to the boiling system gives promise of a self-regulating method to increase boiling heat transfer when required, and is the most significant new finding of this investigation. Two pertinent Russian papers were translated and are appended."

A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.

Details are given of an apparatus used to dissolve irradiated ceramic, metallic, and carbide fuel specimens, to dilute the dissolver solutions accurate to a known volume, and to take aliquots with a specially adapted automatic burette. Procedures for its use are given.

A method is described for the computation of the energy dependence of the neutron flux and slowing down density in a bare reactor to form the basis of a 7090 Fortran computer program for survey studies of power reactors. Allowance is made for resonance absorption and resonance fission, neutron thermalisation, fast neutron reactions including (n, 2n) and (n, n), and anisotropic elastic scattering.

"Uranium and zirconium were bonded by melting the two metals in contact with one another in a bimetallic casting process. Tensile tests of specimens containing the original zone of interface between the two metals showed that all failures were at locations other than the interface. The coefficients obtained for diffusion between molten uranium and molten zirconium varied from 2.13 cm squared per day at 3,380 degrees F. to 9.17 cm squared per day at 3,510 degrees F. the activation energy for the diffusion process was calculated to be 182,000 calories per gram mole."

Technical report. From Abstract : "Accurate measurements on boiling points and surface tensions of mixtures of benzyl acetate with dioxan, aniline and meta-cresol over the entire range of concentration are reported. The results have been analysed in terms of quasi-crystalline model which is partially successful in representing the composition dependence of heats of mixing, boiling points and surface tension except for composition dependence of boiling points of benzyl acetate and meta-cresol."

Technical report outlining the element calcium as well as its occurrences, physical properties, chemical properties, methods of manufacture, economic aspects, and uses.

"A comparison of grafting to two thicknesses of polypropylene film is made using isotope and electron accelerator initiation. The results indicate that the grafting of methacrylic acid: styrene to polypropylene is mainly a surface reaction."

Ever since the existence of a bound state of Hydrogen was discovered, it has been uncertain whether any other bound states existed. In addition to its importance in astrophysics this question has also come up in discussions of the scattering of electrons from hydrogen. To settle this problem it is necessary to calculate lower bounds for the eigenvalues of the Schrodinger equation. A simple calculation has been carried out for the problem of the negative hydrogen ion.

The purpose of the Computer Information Center is to stimulate the production of documentation and to make it readily available to computer users within the Laboratory. In addition, the Center will endeavor to obtain all publications of programming and machine manuals pertinent to LRL.For the Computer Information Center to be effective, it is essential that its coverage be as complete as possible. Computer users who have written programs or subroutines are therefore urged to submit write-ups for publication to Chet McIntosh (Bldg. 161 - Room 1241) or Nora Kegel (Bldg. 161 - Room 1239). All materials presented will be edited and the final draft returned to the author for verification prior to publication within the Laboratory.

Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.

Tests in a one-fifth scale clear plastic model were conducted to investigate the flow characteristics of the asymmetrical riser configuration in the Consumers Big Rock power plant.

The Heavy Water Components Test Reactor (HWCTR) is used to test prototype fuel elements for power reactors that are moderated with heavy water and fueled with natural or slightly enriched uranium. During the initial critical experiments in the HWCTR, it was observed that there were unexpected variations in nuclear reactivity. Investigations revealed that this effect was due to bubble of helium gas appearing and disappearing in the moderator. An examination of the expected operating conditions of the HWCTR and the solubility of helium in D2O showed that it was possible during normal operation for the helium content of the moderator to exceed saturation and thus for helium to appear as bubbles in the moderator. The possibility of helium bubbles appearing in the moderator because of solubility characteristics was eliminated by modifications to the process system so as to maintain the gas content of the moderator appreciably below saturation.

Montgomery and Chandrasekhar and Hulm suggested models for predicting Im and Hm of high-field superconducting solenoids. Montgomery's model for predicting the degradation effect of superconducting solenoids leads to a unique coil quenching characteristics if geometrically similar solenoids are considered. Experiments do not verify these predicted results. Chandrasekhar and Hulm's model leads to one unique coil quenching characteristic for all solenoids with identical wire type and turn distance; coils with identical load factor should display identical values im and Hm. An analysis of the surface currents in an ideal superconducting infinitely long solenoid demonstrated possible forms of shielding currents. Experiments with Pb coils with and without NbZr and compensation agree with results expected from this analysis, but contradict Chandrasekhar and Hulm's model. Measurements of individual turn resistances show behavior of a soft superconductor solenoid in the intermediate state.

An incident is described concerning a curium accelerator target aerolized by explosion. Management of the spill, sampling, particle sizing, and medical findings are presented. Seven of the 27 persons present showed low levels of curium excretion. The data from this incident were compared with those from three other inhalation exposures to curium compounds at Lawrence Laboratory.

Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the criteria are included.

This technical report provides design criteria for reactor test facilities utilizing existing structures at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of facilities providing the capability for installation, extended nuclear testing and remote disassembly of the 10mw Lithium-Cooled Reactor Experiment (LCRE). Facility structural and process design has been developed to the extent required to assure the safety and technical feasibility of the proposed facilities for reactor operation.

This technical report provides a design criteria for a technical support facility for the Lithium Cooled Reactor Experiment (LCRE) and SNAP-50-DR-1 Test Facilities. The support facility is adjacent to the LCRE Test Facility and is located completely within the existing Building 629 structure at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of laboratories, shops and engineering areas required to support the installation, operation, maintenance and disassembly of the LCRE and SNAP-50 tests. The construction and modification required to adapt the building to reactor test support operations are described in detail in the following report.

Methods are described for the determination of traces of Be, Th, and U in concentrated sulfuric-phosphoric acid mixtures. When the Be concentration is sufficiently high, the chrome azurol S spectrophotometric method may be applied directly, and a small correction made for phosphate interference. At lower concentrations Be should be first separated by an acetylacetone extraction. Th must be separated from sulfate and phosphate before the thoronol spectrophotometric method can be used. This is achieved by precipitating Th as the fluoride, using Y carrier. U may be determined spectrophotometrically with arsonazo after separating Be, Th, suIfate, phosphate, and other impurities by anion-exchange from hydrochloric acid solution. In an alternative procedure, U is reduced to the tetravalent state and precipitated with Th as the fluoride, again using Y carrier. The determination is then completed by a-c polarography.

Technical report. From Abstract : "An analytical method was developed for the determination of Np237 in solutions that contain plutonium and fission products. Np (IV) was extracted into tri-n-octylamine. A quantitative recovery of a Np237 standard was obtained with a coefficient of variation of 1.0% (n=10). A coefficient of variation of 3% was obtained for seven analyses of a process sample."